Thank you for your patience as the publications list loads to the page.
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | FY2016 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | FY2016 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | FY2016 | |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | FY2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | FY2016 |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | FY2016 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | FY2016 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | FY2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | FY2016 | |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OÂBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | FY2016 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | FY2016 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | FY2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | FY2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | FY2016 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | FY2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | FY2016 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | FY2016 | |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | FY2016 | |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | FY2016 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | FY2016 | |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | FY2016 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | FY2016 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | FY2016 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | FY2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | FY2016 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | FY2016 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | FY2016 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | FY2016 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Cole, J. I., T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | FY2010 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | FY2016 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | FY2016 | |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | FY2016 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OÂBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | FY2016 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | FY2016 | |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | FY2016 | |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | FY2016 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | FY2016 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | FY2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | FY2011 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | FY2016 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(1-3), 2-7. | Publication | FY2011 |
| OÂBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | FY2016 | |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | FY2016 |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| Cole, J. I., O'Holleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | FY2011 | |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | FY2016 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Hurley, D. H., Khafizov, M., Shinde, S., Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | FY2011 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Janney, D. E., Kennedy, J. R. (2010). As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | FY2011 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | FY2016 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | FY2016 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | FY2016 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., Sohn, Y. H. (2011). Thermotransport in γ(bcc) U-Zr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | FY2011 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | FY2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | FY2016 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | FY2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | FY2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | FY2016 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | FY2016 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | FY2016 | |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | FY2016 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | FY2016 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | FY2016 | |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | FY2016 |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | FY2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | FY2016 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | FY2016 | |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | FY2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | FY2016 | |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | FY2016 | |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Mariani, R. D., Porter, D. L., O'Holleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | FY2012 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | FY2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | FY2016 | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | FY2016 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | FY2016 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | FY2016 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | FY2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 2089-2107. | Publication | FY2013 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | FY2016 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | FY2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | FY2016 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(1-3), 1-8. | Publication | FY2013 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | FY2016 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of U-Pu-Zr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | FY2013 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | FY2017 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | FY2017 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | FY2017 | |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | FY2017 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | FY2017 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417-428. | Publication | FY2013 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I-Mechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | FY2013 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II- Mechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | FY2013 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155-163. | Publication | FY2013 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | FY2017 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | FY2017 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1-yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | FY2013 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | FY2017 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgO-Nd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | FY2013 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | FY2017 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Park, Y., Huang, K., Paz y Puente, A., et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 72-82. | Publication | FY2013 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145-154. | Publication | FY2013 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | FY2017 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | FY2013 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | FY2017 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF. Journal of Nuclear Materials, 428(1-3), 170-175. | Publication | FY2013 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | FY2017 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems  Water Reactors. | Publication | FY2017 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | FY2017 | |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9-y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | FY2013 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | FY2017 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | FY2017 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(1-3), 206-213. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | FY2017 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | FY2017 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | FY2017 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | FY2017 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | FY2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | FY2017 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 - The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | FY2014 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | FY2017 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(1-3), 263-272. | Publication | FY2014 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | FY2017 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(1-3), 290-299. | Publication | FY2014 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(1-3), 39-48. | Publication | FY2014 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | FY2017 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | FY2017 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction. Journal of Nuclear Materials, 448(1-3), 534-540. | Publication | FY2014 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | FY2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238-251. | Publication | FY2014 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | FY2017 | |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | FY2017 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(1-3), 162-167. | Publication | FY2014 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(1-3), 497-511. | Publication | FY2014 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | FY2017 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | FY2017 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(1-3), 441-447. | Publication | FY2014 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | FY2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(1-3), 520-533. | Publication | FY2014 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 14-17, 2014. | Publication | FY2014 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | FY2017 | |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh,; J. Mat (Eds.), Ceramic Materials for Energy Applications IV. | Publication | FY2014 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | FY2017 | |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | FY2017 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | FY2017 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(1-3), 323-333. | Publication | FY2014 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | FY2017 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | FY2017 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | FY2017 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(1-3), 304-310. | Publication | FY2014 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | FY2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2-MgAl2O4-CeMgAl11O19) and four-phase (3Y-TZP-Al2O3-MgAl2O4-LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | FY2015 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | FY2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | FY2017 | |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | FY2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | FY2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | FY2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., O'Brien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | FY2015 | |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | FY2017 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-Y-O system. Journal of Nuclear Materials, 460, 5-12. | Publication | FY2015 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | FY2017 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | FY2017 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UN-U3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | FY2015 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | FY2017 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system - FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | FY2015 | |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | FY2017 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | FY2017 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | FY2015 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | FY2018 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523-537. | Publication | FY2015 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | FY2018 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | FY2018 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | FY2018 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | FY2018 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | FY2018 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | FY2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | FY2018 | |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | FY2018 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | FY2018 | |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 15-21, 2013. ASME. | Publication | FY2015 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | FY2018 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ~295 °C to ~6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | FY2015 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | FY2018 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-La-O system. Journal of Nuclear Materials, 456, 142-150. | Publication | FY2015 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | FY2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | FY2018 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 13-17, 2014 | Publication | FY2015 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | FY2018 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Robb, K. R., & Powers, J. J. (2014, October 27-30). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | FY2015 | |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | FY2018 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | FY2018 | |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | FY2018 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | FY2018 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 670-1498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | FY2015 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | FY2018 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | FY2018 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | FY2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b, INL/EXT-14-33641, Rev 0, November 2014. | FY2015 | |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | FY2018 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., O'Brien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | FY2015 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | FY2018 | |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | FY2016 | |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | FY2018 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | FY2018 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | FY2018 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Âeve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold sprayÂcoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | FY2018 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | FY2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | FY2018 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | FY2018 | |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | FY2018 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | FY2018 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | FY2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxideÂsilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | FY2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | FY2016 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | FY2019 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | FY2019 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | FY2019 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | FY2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | FY2019 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | FY2019 |
| Publication | ||
| Publication | ||
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | FY2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | FY2019 | |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | FY2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | FY2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | FY2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) Â A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | FY2019 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | FY2019 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 1-5, 2016 | Publication | FY2016 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | FY2019 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | FY2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | FY2019 | |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 1703Â1709. | Publication | FY2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | FY2019 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., O'Brien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | FY2019 | |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., O'Brien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | FY2016 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | FY2019 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | FY2016 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | FY2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | FY2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | FY2019 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program - current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | FY2016 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | FY2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | FY2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | FY2019 | |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | FY2016 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | FY2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | FY2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | FY2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | FY2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | FY2019 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | FY2019 | |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | FY2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | FY2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | FY2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | FY2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 17-20, 2016. | Publication | FY2016 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | FY2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | FY2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | FY2019 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 17-21, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | FY2016 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | FY2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | FY2019 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | FY2019 | |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | FY2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | FY2019 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | FY2019 | |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | FY2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | FY2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | FY2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | FY2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | FY2019 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | FY2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | FY2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | FY2019 |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | FY2019 | |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | FY2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | FY2019 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O'Brien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1-5, 2016. | FY2016 | |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | FY2016 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | FY2017 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA's Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea, September 2017 | FY2017 | |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on "In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures". Journal of Nuclear Materials, 484, 168-173. | Publication | FY2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | FY2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 1475-1483). | Publication | FY2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDE-pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | FY2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1-x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | FY2017 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 6429-6434. | Publication | FY2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176-185. | Publication | FY2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 1484-1492. | Publication | FY2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 1373-1382. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™. Journal of Nuclear Materials, 507, 306-315. | Publication | FY2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269-272. | Publication | FY2018 |
| Kilby S.M, Marshall M.A, Choe D.O. et al. (2024). Design of Mini-Plate-1 Irradiation Test for Qualification of High-Density, Low-Enriched U-10Mo Monolithic Fuel. JOM. | Publication | FY2025 |
| Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C. & M. Tippet (2024). Fast Neutron Irradiation Capability in Existing Thermal Test Reactors, Annals of Nuclear Energy, Volume 207, 110731, ISSN 0306-4549. | Publication | FY2025 |
| Wang, Y., Burns, J., Yao, T. & L. Capriotti (2024). Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155209, ISSN 0022-3115. | Publication | FY2025 |
| Wang, Y., Howard, C., Xu, F., Salvato, D., Bawane, K., Murray, D., Frazer, D., Anderson, S., Yao, T., Yeo, S., Kim, J-H, Lee, B-O, Kim, J., Fielding, R. & L. Capriotti (2024). Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155231, ISSN 0022-3115. | Publication | FY2025 |
| Nicodemo G., Zullo G., Cappia F., Van Uffelen P., De Lara A., Luzzi L. & D. Pizzocri (2024). Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity. Journal of Nuclear Materials. 601:155301. | Publication | FY2025 |
| Colldeweih A., P. Petersen, M. Matos, J. Stockwell, R. Hansen, D. Kamerman, D. Lutz & F. Cappia (2025) Post irradiation examinations of FeCrAl cladding in PWR conditions Journal of Nuclear Materials Vol. 603, 155402 | Publication | FY2025 |
| Dabney, T., Sasidhar, K.N., Willing, E., Lukas, C., Quillin, K., Yeon, H. & K. Sridharan (2025). Microstructural Evolution in Ion Irradiated Cold Spray Cr Coated Zr-alloy, Journal of Nuclear Materials, vol. 606, 155652 | Publication | FY2025 |
| Chen, D., Burns, J., Wright, K. E., Salvato, D., Yao, T. & L. Capriotti (2025). Transmission electron microscopy characterization of fuel cladding chemical interaction between minor actinides bearing U-Pu-Zr fuel and AIM1 cladding. Journal of Nuclear Materials, 607, 155667. | Publication | FY2025 |
| Kancharla R.R, Chuirazzi W.C, Kane J.J et al. (2025). X-ray computed tomography of deconsolidated TRISO particles from the AGR-5/6/7 irradiation experiment capsule 1 compact. J Nucl Mater. ; 607:155704. doi:10.1016/j.jnucmat.2025.155704. | Publication | FY2025 |
| Meehan N.A., Gorton J.P., Capps N.A. & N.R. Brown (2025). Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions. Journal of Nuclear Materials, 2025;609:155745. doi:10.1016/j.jnucmat.155745. | Publication | FY2025 |
| Middlemas, S., & C. Adkins (2025). A critical analysis of U-Pu-Zr phase transitions using calorimetric, microstructural, and phase equilibria data. Journal of Nuclear Materials, 612, 155778. | Publication | FY2025 |
| Probert A., Swearingen A., Schulthess J., Capriotti L., Jensen C. & A. Aitkaliyeva (2025). Comparative Post-irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Steady-state Irradiation Behavior Against Historical and Modeled Fuel Performance. Journal of Nuclear Materials.; 610:155782. | Publication | FY2025 |
| Dhulipala, S. L. N., Simon, P.-C. A., Demkowicz, P. A., Hirschhorn, J. A. & S. R. Novascone (2025). Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches. Journal of Nuclear Materials, 610, 155795. | Publication | FY2025 |
| Salvato, D., Nguyen, B.-P., Wang, Y., Di Lemma, F. G., Capriotti, L., Aitkaliyeva, A. & T. Yao, (2025). TEM Characterization of Two Variants of Fuel Cladding Chemical Interaction in a HT-9 Clad U-10Zr Fuel. Variant 1: FCCI with a Zr Rind. Journal of Nuclear Materials, 614, 155855. | Publication | FY2025 |
| Espersen, J. I., Garrison, B. E., Cervenka, P., Seshadri, A., Linton, K., Shirvan, K., Capps N.A & N.R. Brown (2025). The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions. Journal of Nuclear Materials, 155910. | Publication | FY2025 |
| Skerjanc, W. F., Jiang, W., Demkowicz, P. A. & J.D. Stempien (2025). Evaluation of AGR-3/4 In-pile Silver Release Predictions Against Post-irradiation Examination measurements. Journal of Nuclear Materials, 615, 155942. | Publication | FY2025 |
| Mauseth, T., Dunzik-Gougar, M. L. & F. Teng (2025). Micro-tensile Characteristics of As-fabricated and Irradiated AGR-2 TRISO Fuel Particle Buffer, IPyC, and Buffer-IPyC Interlayer Regions. Journal of Nuclear Materials, 156086. | Publication | FY2025 |
| Capriotti, L., Di Lemma, F., Salvato, D., Xu, F., Tang, Y., Paaren, K.M., Swearingen, A.L., Jensen, C.B., Wang, Y. & D.L. Porter (2025). An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in HT9/U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis. Journal of Nuclear Materials, p.156092. | Publication | FY2025 |
| Pradhan A, Xu F, Salvato D, et al. (2024). Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning. Mater Charact. 2024;218(1):114524. | Publication | FY2025 |
| Rittenhouse J., Pradhan A., Kamerman D.W, Burns J., Xu F., Wen H. & T. Yao (2025) Site-specific Nanoscale Characterization of Zirconium Hydrides in the Hydride Rim Structure of Hydrogen-charged Zircaloy-4 Cladding. Mater Charact ;224:115006. | Publication | FY2025 |
| Yang, G., Nguyen, B.-P., Rittenhouse, J. E., Xu, F., Gonderman, S., Gazza, J., Xu, P. & T.Yao (2025). Investigating Grain Structure and Microcracking in SiCf-SiCm Composites Using 4D-STEM. Materials Characterization, 225, 115165. | Publication | FY2025 |
| Zhao, L., Xu, F., Porter, D. L. & Y. Wang (2025). Quantification of line dislocations in FFTF irradiated HT9 cladding by deep learning method. Materials Characterization, 227, 115322. | Publication | FY2025 |
| Beausoleil, G. L., Curnutt, B., Moorehead, M. & Bascom, A. (2025). Multi-principal element alloys for fast reactor cladding applications. Nuclear Engineering and Technology, 57(4), 103303. | Publication | FY2025 |
| Chuirazzi, W., Bush, J., Gross, B., Bryant, M., Clark, K., Cook, M., Burtenshaw, J., Price, J., Morankar, S., Blattner, M., Landon, R., Galloway, K., Stanger, J., Stamos, R., Duke, J., Watt, C. & J. Stempien (2025). Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel. Nuclear Engineering and Technology, 57(10), 103726. | Publication | FY2025 |
| Seo S., Folsom C., Jensen C. et al. (2024). International Fuel Performance Study of Fresh Fuel Experiments for PCMI Effects During RIA Experiments. Nuclear Engineering and Design; 430:113673. | Publication | FY2025 |
| Moussaoui, M. A., Anderson, K. S., Yoo, J., & N.E. Woolstenhulme (2025) Device for steam cladding oxidation testing at TREAT, Nuclear Engineering and Design, 445, 114441. | Publication | FY2025 |
| Downey C.M., Oldham N., Fleming A., Chapman D., Mata Cruz A. & K. Ellis (2024). Design of a First-of-a-kind Instrumented Advanced Test Reactor Irradiation Capsule Experiment for in Situ Thermal Conductivity Measurements of Metallic Fuel. Prog Nucl Energy.;175:105325. | Publication | FY2025 |
| Umretiya, R.V, Qu, H., Yin, L., Jurewicz, T.B., Gupta, V.K., Drobnjak, M., Knussman, M. Hoffman, A.K. & R.B. Rebak (2024). Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments, npj Mater Degrad 8, 88. | Publication | FY2025 |
| Zhao, L., Wang, Y., & F. Xu (2025). Accurate Segmentation of Localized Fuel Cladding Chemical Interaction Layers in SEM Micrographs with Deep Learning Method. Scientific Reports, 15, 28878. | Publication | FY2025 |
| Chavez, R., Anand, N.K. & Hassan, Y. & S. Girimaji (2024) "Flow Over a Sphere at Elevated Pressures: An Analysis of the Near-Wake Using Spectral Proper Orthogonal Decomposition" Physics of Fluids, November 2024, Vol. 36, 115155 (1-17) Issue 11, selected as Editors Pick. | Publication | FY2025 |
| Hawkes, G., Pham, B. & C. Otani (2024). Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps. Nuclear Science and Engineering, 126. | Publication | FY2025 |
| Riet, A. A. & J.D. Stempien (2025). Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation. Nuclear Science and Engineering, 112. | Publication | FY2025 |
| Petersen, P. G., Hansen, R. S., Cappia, F., Kamerman, D., Baird, K. & C. Christensen (2024). Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens. Journal of Testing and Evaluation, 52(6), 33263345. | Publication | FY2025 |
| Capps, N., Yan, Y., Harp, J., Ridley, M. & R. Salko Jr. (2024). Recent High Burnup LOCA Testing at Oak Ridge National Laboratory (ORNL/SPR-2024/3544). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Singh G., Yu J., Xu F., Yao T. & P. Xu (2024). Multiscale Modeling of Silicon Carbide Cladding for Nuclear Applications: Thermal Performance Modeling. Energies. 2024; 17(23):6124. | Publication | FY2025 |
| Cakmak, E., Cinbiz, M. N., Arregui-Mena, J. D., Deck, C. & T. Koyanagi (2025). Damage Progression and Failure of SiC/SiC Composite Tubes under Hard-Contact Radial Expansion. Composites Part B: Engineering, 112869. | Publication | FY2025 |
| Dolley, E. J., Zhang, W., Zorn, G., Sand, T. & R.B. Rebak (2024) "Enhanced mechanical properties and wear resistance of FeCrAl alloys at~ 300 C and Higher temperatures." JOM 76, no. 8 (2024): 4123-4130. | Publication | FY2025 |
| Nagothi, B.S., Qu, H., Zhang, W., Umretiya, R.V., Dolley, E.& R.B. Rebak (2024). "Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding." Materials 17, no. 7: 1633. | Publication | FY2025 |
| Qu, H., Yin, L., Larsen, M., and R.B. Rebak (2024). "Distinctive oxide films develop on the surface of fecral as the environment changes for nuclear fuel cladding." Corrosion and Materials Degradation 5, no. 1: 109-123. | Publication | FY2025 |
| Woolstenhulme, N. et al. (2025). SPARC - Plans for a New Critical Experiment Facility with a Horizontal Split Table (INL/RPT-25-84855). Idaho National Laboratory, Idaho Falls, ID. | Publication | FY2025 |
| Yang, Y., Weicheng Z. & C. Massey (2025). Computational Design of Improved Fast Reactor Cladding (ORNL/TM-2025/3953), Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., Laug, D.V. & J.D. Stempien (2024). Micro-tensile Properties of Fueled Irradiated AGR-2 TRISO-coated Particle Buffer, IPyC, and SiC Interlayer Regions. Presented at the 2024 Nuclear Materials (NuMat) Conference. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L. & J.D. Stempien (2024). Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., & J.D. Stempien (2024). Fracture Behavior Considerations for the TRISO Particle Matrix. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles. Presented at the 2025 Nuclear Science User Facilities (NSUF) Annual Program Review. | Publication | FY2025 |
| Qu, H.J., Chikhalikar, A.S., Abouelella, H., Roy, I., Rajendran, R., Nagothi, B.S., Umretiya, R., Hoffman, A.K. & R.B. Rebak (2024). "Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments." Corrosion Science 229 (2024): 111870. | Publication | FY2025 |
| Roy, R., Chatterjee, A., Mondal, S., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya.(2025). "Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions." Corrosion Science: 112965. | Publication | FY2025 |
| Mondal, S., Chatterjee, A., Roy, R., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya. "Synergistic Roles of Cr and Mo in Low Temperature Steam Oxidation of FeCrAl Alloys." Corrosion Science (2025): 113107. | Publication | FY2025 |
| Rajendran, R., Chikhalikar, A.S., Roy, I., Abouelella, H., Qu, H.J., Umretiya, R.V., Hoffman, A.K., and R.B. Rebak (2024). "Effect of aging and ?segregation on oxidation and electrochemical behavior of FeCrAl alloys." Journal of Nuclear Materials 588: 154751. | Publication | FY2025 |
| Joyce, L., Wang, P., Umretiya, R.V., Hoffman, A. & Y. Xie (2024). "Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water." Journal of Nuclear Materials 593: 154987. | Publication | FY2025 |
| Chikhalikar, A.S., Qu, H., Abouelella, H., Nagothi, B., Rajendran, R., Roy, I., Umretiya, R., Hoffman, A. & R. Rebak, . "Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys." Journal of Nuclear Materials 598 (2024): 155179. | Publication | FY2025 |
| Nelson M., Samuha S., Kombaiah B., Kamerman D. & P. Hosemann (2024). Enhanced Stress Relaxation Behavior Via Basal ?a?dislocation activity in Zircaloy-4 cladding. Journal of Nuclear Materials ;601:155337. | Publication | FY2025 |
| Hirschhorn J.A., Aagesen L.K., Jiang C. & G.L. Beausoleil (2025). Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nucl Eng Des ;432:113811. | Publication | FY2025 |
| Ravi, S.K., Comlek, Y., Pathak, A., Gupta, V., Umretiya, R., Hoffman, A., Pilania, G. et al. (2025) "Interpretable multi-source data fusion through Latent Variable Gaussian Process." Engineering Applications of Artificial Intelligence 145: 110033. | Publication | FY2025 |
| Umretiya, R.V., Chikhalikar, A., Elward, B., Moreira, T.A., Anderson, M., Rebak, R.B. & J.V. Rojas (2024). "The Effect of Ramp Heating on the Microstructure and Surface Chemistry of APMT FeCrAl Alloy." Nuclear Materials and Energy 38: 101567. | Publication | FY2025 |
| Joyce, L., Umretiya, R.V., Qu, H., Shang, Z. & Y. Xie (2025). "Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400900° C." Nuclear Materials and Energy : 101953. | Publication | FY2025 |
| Bermudez, S., Erdogan, F., Davis, V., Rojas, J.V. & R.V. Umretiya (2025). "Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000° C)." Nuclear Materials and Energy : 101972. | Publication | FY2025 |
| Bawane, K.K., Yang, G., Yao, T., Xu, F., Xu, P., Gonderman, S. & J. Gazza (2025). Microstructure Analysis of Silicon Carbide Cladding Using 4D-STEM. Paper presented at M&M 2025. | FY2025 | |
| Cappia F., Colldeweih, A., Frazer, D., Hansen, R., Petersen, P., Stockwell, J., Anderson, S., Charbeneau, J., Kamerman, D. (2024) Effect of Metal Contaminants on Cr Coating Performance after Irradiation in the Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Carvajal, J. (2025). In-Rod Sensor System Irradiation Test Results with Segmented Fuel Assembly, accepted for the 14th International Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2025), Chicago. | FY2025 | |
| Cervenka, P., Seshadri A., Sevecek M., Cvrcek L. & K. Shirvan (2024). Development of PVD Cr-(Nb) coated fuel cladding with enhanced accident tolerance, Presented at the Nuclear Materials Conference. | FY2025 | |
| Chavez, R. (2025). Fluid Dynamics and Thermal Effects of Flow Over a Sphere at High Pressures and Graphitic Dust Behavior in Square Channels, PhD Dissertation, Texas A&M University. | FY2025 | |
| Chavez, R., Anand, N.K. & Y. Hassan (2025) High-Pressure Experimental Analysis of Thermal Effects on Near-Wake Turbulence and Energy Distribution of Flow over a Heated Sphere, Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Colldeweih A., Kamerman, D., Matos, M., Bawane, K., J. Stockwell, J., A. Pradhan, A., Hansen, R., Cappia, F. & D. Lutz (2024) Corrosion of Neutron Irradiated FeCrAl in the ATR Water Loop TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Dabney, T., Sasidhar, K.N., Willing, E., Eftink, B., Li, N., Maier, B., Walters, J. & K. Sridharan (2025). Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding, Symposium on Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Hansen R., Colldeweih, A., Petersen, P., Stockwell, J., Charboneau, J., Albuquerque, L., Baird, K., Kamerman, D. & F. Cappia (2024) Examinations of Cr-Coated M5 Cladding Irradiated at the INL Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Harp, J., Yan, Y., Morris, R., Baldwin, C., Jones, M. & N. Capps (2024). Development of Fission Gas Release Cabilities to Study High Burnup Commercial Fuel Performance under Loss of Coolant Accident Conditions. Proc. TopFuel 2024, Grenoble, France. | FY2025 | |
| Jung, W., Dunbar, C., Jo, J.Y., Sridharan, K. & H. Yeom (2025). Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr cladding under Multiple Quench Tests, Symposium on Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Karlsson, T. Y. (2025). Fuel Qualification: Near-Term Activities & Needs for Molten Salt Fuels. Presented at the EPRI Advanced Reactor Workshop. | FY2025 | |
| Kosmidou, M., Broussard, A., Lian, J. & E. Kardoulaki (2025). Filling of data gaps for the development of ceramic fuels, pp. 23.Materials in Nuclear Energy Systems (MiNES) 2025 Conference. | FY2025 | |
| Li, N., Xie, D., Kim, H., Dabney, T., Eftink, B., Sridharan, K., Graening, T., Nelson, A., Fensin, S.& S. Maloy (2025). In Situ Micro-Cantilever Beam Bending Tests to Assess the Adhesion Strength of Cr Coatings on Zry-4, Symposium on Mechanical Behavior Related to Interface Physics IV, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Microstructural Characterization of AGR-2 TRISO Particle Buffer, IPyC, and Buffer-IPyC Interfaces. Presented at the 2025 Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). | FY2025 | |
| Pham, B. T., Hawkes, G. L., Lybeck, N. J., Otani, C. & P.A. Demkowicz (2025). Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment. Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Seshadri A., Cervenka P., Fazi A., Sevecek M., Carpenter D., Cetiner N., Motta A., Ishak C., Fei Z., Raiman S., Xu P. & K. Shirvan. In-pile hydrothermal corrosion behavior of Zirconium Alloys with and without ATF Coatings, Presented at 21st ASTM International Symposium on Zirconium in the Nuclear Industry. | FY2025 | |
| Shirvan K., Cervenka P., Fazi A. & A. Seshadri (2025). Experimental Investigation of CrNb Coatings for PWRs and BWRs. Paper at the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. | FY2025 | |
| Sridharan, K. Maier, B., Dabney, T., Willing, E., Pocquette, N. Lukas, C., Anderson, N. & H. Yeom (2025). Cold Spray Materials Deposition Technology for Nuclear Energy Systems, Symposium on Advances in Materials Deposition by Cold Spray and Related Technologies, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Walter, J., Roberts, E., Fredrick, K., Viands, D. & X. Huang (2025). The Effect of Chromium Coating Microstructure and Oxide Films on Hydrogen Uptake in Zirconium-alloy Nuclear Fuel Cladding, 21st International Symposium on Zirconium in the Nuclear Industry, Aix-en-Provence, France. | FY2025 | |
| Woolstenhulme, N., Martin, N., DeHart, M., Percher, C., Cutler, T., Wieselquist, W. (2025). SPARC, an Effort to Reestablish a Horizontal Split Table Critical Facility for HALEU Experiments and Beyond. Paper presented at the NCSD 2025 Annual Meeting. | FY2025 | |
| Yuan, G., Cook, D.H., Barnard, H., Lahoda, E., Xu, P., Ritchie, R.O. & D. Liu (2025). Improved Damage Tolerance of SiC-Based Nuclear Fuel Cladding with Novel Multi-Layered SiC Coating Design at 1200°C, Materials & Design, Volume 256, August 2025, 114260. | Publication | FY2025 |
| Zhang, S., Ma, Z., Xu, P. (2024). Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors, 2024 ANS Annual Meeting. | FY2025 | |
| Zhang, J., Xu, P., Sevecek, M., Sim, K.S. & A. Khaperskaia (2025). Contribution of IAEA Coordinated Research Projects to Light Water Reactors Advanced Technology Fuel Testing and Simulation, Nuclear Engineering and Design 418, 112910. | Publication | FY2025 |
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | FY2016 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | FY2016 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | FY2016 | |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | FY2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | FY2016 |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | FY2016 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | FY2016 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | FY2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | FY2016 | |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OÂBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | FY2016 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | FY2016 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | FY2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | FY2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | FY2016 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | FY2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | FY2016 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | FY2016 | |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | FY2016 | |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | FY2016 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | FY2016 | |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | FY2016 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | FY2016 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | FY2016 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | FY2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | FY2016 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | FY2016 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | FY2016 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | FY2016 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Cole, J. I., T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | FY2010 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | FY2016 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | FY2016 | |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | FY2016 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OÂBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | FY2016 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | FY2016 | |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | FY2016 | |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | FY2016 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | FY2016 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | FY2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | FY2011 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | FY2016 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(1-3), 2-7. | Publication | FY2011 |
| OÂBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | FY2016 | |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | FY2016 |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| Cole, J. I., O'Holleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | FY2011 | |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | FY2016 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Hurley, D. H., Khafizov, M., Shinde, S., Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | FY2011 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Janney, D. E., Kennedy, J. R. (2010). As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | FY2011 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | FY2016 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | FY2016 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | FY2016 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., Sohn, Y. H. (2011). Thermotransport in γ(bcc) U-Zr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | FY2011 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | FY2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | FY2016 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | FY2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | FY2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | FY2016 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | FY2016 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | FY2016 | |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | FY2016 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | FY2016 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | FY2016 | |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | FY2016 |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | FY2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | FY2016 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | FY2016 | |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | FY2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | FY2016 | |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | FY2016 | |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Mariani, R. D., Porter, D. L., O'Holleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | FY2012 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | FY2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | FY2016 | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | FY2016 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | FY2016 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | FY2016 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | FY2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 2089-2107. | Publication | FY2013 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | FY2016 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | FY2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | FY2016 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(1-3), 1-8. | Publication | FY2013 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | FY2016 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of U-Pu-Zr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | FY2013 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | FY2017 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | FY2017 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | FY2017 | |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | FY2017 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | FY2017 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417-428. | Publication | FY2013 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I-Mechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | FY2013 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II- Mechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | FY2013 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155-163. | Publication | FY2013 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | FY2017 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | FY2017 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1-yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | FY2013 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | FY2017 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgO-Nd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | FY2013 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | FY2017 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Park, Y., Huang, K., Paz y Puente, A., et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 72-82. | Publication | FY2013 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145-154. | Publication | FY2013 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | FY2017 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | FY2013 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | FY2017 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF. Journal of Nuclear Materials, 428(1-3), 170-175. | Publication | FY2013 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | FY2017 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems  Water Reactors. | Publication | FY2017 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | FY2017 | |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9-y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | FY2013 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | FY2017 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | FY2017 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(1-3), 206-213. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | FY2017 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | FY2017 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | FY2017 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | FY2017 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | FY2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | FY2017 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 - The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | FY2014 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | FY2017 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(1-3), 263-272. | Publication | FY2014 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | FY2017 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(1-3), 290-299. | Publication | FY2014 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(1-3), 39-48. | Publication | FY2014 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | FY2017 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | FY2017 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction. Journal of Nuclear Materials, 448(1-3), 534-540. | Publication | FY2014 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | FY2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238-251. | Publication | FY2014 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | FY2017 | |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | FY2017 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(1-3), 162-167. | Publication | FY2014 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(1-3), 497-511. | Publication | FY2014 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | FY2017 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | FY2017 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(1-3), 441-447. | Publication | FY2014 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | FY2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(1-3), 520-533. | Publication | FY2014 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 14-17, 2014. | Publication | FY2014 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | FY2017 | |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh,; J. Mat (Eds.), Ceramic Materials for Energy Applications IV. | Publication | FY2014 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | FY2017 | |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | FY2017 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | FY2017 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(1-3), 323-333. | Publication | FY2014 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | FY2017 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | FY2017 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | FY2017 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(1-3), 304-310. | Publication | FY2014 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | FY2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2-MgAl2O4-CeMgAl11O19) and four-phase (3Y-TZP-Al2O3-MgAl2O4-LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | FY2015 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | FY2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | FY2017 | |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | FY2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | FY2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | FY2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., O'Brien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | FY2015 | |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | FY2017 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-Y-O system. Journal of Nuclear Materials, 460, 5-12. | Publication | FY2015 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | FY2017 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | FY2017 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UN-U3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | FY2015 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | FY2017 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system - FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | FY2015 | |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | FY2017 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | FY2017 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | FY2015 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | FY2018 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523-537. | Publication | FY2015 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | FY2018 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | FY2018 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | FY2018 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | FY2018 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | FY2018 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | FY2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | FY2018 | |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | FY2018 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | FY2018 | |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 15-21, 2013. ASME. | Publication | FY2015 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | FY2018 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ~295 °C to ~6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | FY2015 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | FY2018 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-La-O system. Journal of Nuclear Materials, 456, 142-150. | Publication | FY2015 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | FY2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | FY2018 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 13-17, 2014 | Publication | FY2015 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | FY2018 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Robb, K. R., & Powers, J. J. (2014, October 27-30). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | FY2015 | |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | FY2018 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | FY2018 | |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | FY2018 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | FY2018 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 670-1498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | FY2015 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | FY2018 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | FY2018 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | FY2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b, INL/EXT-14-33641, Rev 0, November 2014. | FY2015 | |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | FY2018 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., O'Brien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | FY2015 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | FY2018 | |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | FY2016 | |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | FY2018 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | FY2018 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | FY2018 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Âeve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold sprayÂcoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | FY2018 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | FY2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | FY2018 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | FY2018 | |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | FY2018 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | FY2018 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | FY2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxideÂsilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | FY2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | FY2016 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | FY2019 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | FY2019 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | FY2019 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | FY2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | FY2019 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | FY2019 |
| Publication | ||
| Publication | ||
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | FY2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | FY2019 | |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | FY2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | FY2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | FY2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) Â A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | FY2019 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | FY2019 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 1-5, 2016 | Publication | FY2016 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | FY2019 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | FY2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | FY2019 | |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 1703Â1709. | Publication | FY2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | FY2019 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., O'Brien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | FY2019 | |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., O'Brien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | FY2016 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | FY2019 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | FY2016 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | FY2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | FY2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | FY2019 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program - current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | FY2016 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | FY2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | FY2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | FY2019 | |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | FY2016 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | FY2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | FY2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | FY2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | FY2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | FY2019 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | FY2019 | |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | FY2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | FY2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | FY2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | FY2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 17-20, 2016. | Publication | FY2016 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | FY2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | FY2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | FY2019 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 17-21, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | FY2016 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | FY2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | FY2019 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | FY2019 | |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | FY2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | FY2019 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | FY2019 | |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | FY2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | FY2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | FY2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | FY2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | FY2019 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | FY2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | FY2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | FY2019 |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | FY2019 | |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | FY2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | FY2019 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O'Brien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1-5, 2016. | FY2016 | |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | FY2016 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | FY2017 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA's Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea, September 2017 | FY2017 | |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on "In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures". Journal of Nuclear Materials, 484, 168-173. | Publication | FY2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | FY2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 1475-1483). | Publication | FY2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDE-pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | FY2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1-x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | FY2017 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 6429-6434. | Publication | FY2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176-185. | Publication | FY2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 1484-1492. | Publication | FY2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 1373-1382. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™. Journal of Nuclear Materials, 507, 306-315. | Publication | FY2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269-272. | Publication | FY2018 |
| Kilby S.M, Marshall M.A, Choe D.O. et al. (2024). Design of Mini-Plate-1 Irradiation Test for Qualification of High-Density, Low-Enriched U-10Mo Monolithic Fuel. JOM. | Publication | FY2025 |
| Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C. & M. Tippet (2024). Fast Neutron Irradiation Capability in Existing Thermal Test Reactors, Annals of Nuclear Energy, Volume 207, 110731, ISSN 0306-4549. | Publication | FY2025 |
| Wang, Y., Burns, J., Yao, T. & L. Capriotti (2024). Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155209, ISSN 0022-3115. | Publication | FY2025 |
| Wang, Y., Howard, C., Xu, F., Salvato, D., Bawane, K., Murray, D., Frazer, D., Anderson, S., Yao, T., Yeo, S., Kim, J-H, Lee, B-O, Kim, J., Fielding, R. & L. Capriotti (2024). Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155231, ISSN 0022-3115. | Publication | FY2025 |
| Nicodemo G., Zullo G., Cappia F., Van Uffelen P., De Lara A., Luzzi L. & D. Pizzocri (2024). Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity. Journal of Nuclear Materials. 601:155301. | Publication | FY2025 |
| Colldeweih A., P. Petersen, M. Matos, J. Stockwell, R. Hansen, D. Kamerman, D. Lutz & F. Cappia (2025) Post irradiation examinations of FeCrAl cladding in PWR conditions Journal of Nuclear Materials Vol. 603, 155402 | Publication | FY2025 |
| Dabney, T., Sasidhar, K.N., Willing, E., Lukas, C., Quillin, K., Yeon, H. & K. Sridharan (2025). Microstructural Evolution in Ion Irradiated Cold Spray Cr Coated Zr-alloy, Journal of Nuclear Materials, vol. 606, 155652 | Publication | FY2025 |
| Chen, D., Burns, J., Wright, K. E., Salvato, D., Yao, T. & L. Capriotti (2025). Transmission electron microscopy characterization of fuel cladding chemical interaction between minor actinides bearing U-Pu-Zr fuel and AIM1 cladding. Journal of Nuclear Materials, 607, 155667. | Publication | FY2025 |
| Kancharla R.R, Chuirazzi W.C, Kane J.J et al. (2025). X-ray computed tomography of deconsolidated TRISO particles from the AGR-5/6/7 irradiation experiment capsule 1 compact. J Nucl Mater. ; 607:155704. doi:10.1016/j.jnucmat.2025.155704. | Publication | FY2025 |
| Meehan N.A., Gorton J.P., Capps N.A. & N.R. Brown (2025). Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions. Journal of Nuclear Materials, 2025;609:155745. doi:10.1016/j.jnucmat.155745. | Publication | FY2025 |
| Middlemas, S., & C. Adkins (2025). A critical analysis of U-Pu-Zr phase transitions using calorimetric, microstructural, and phase equilibria data. Journal of Nuclear Materials, 612, 155778. | Publication | FY2025 |
| Probert A., Swearingen A., Schulthess J., Capriotti L., Jensen C. & A. Aitkaliyeva (2025). Comparative Post-irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Steady-state Irradiation Behavior Against Historical and Modeled Fuel Performance. Journal of Nuclear Materials.; 610:155782. | Publication | FY2025 |
| Dhulipala, S. L. N., Simon, P.-C. A., Demkowicz, P. A., Hirschhorn, J. A. & S. R. Novascone (2025). Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches. Journal of Nuclear Materials, 610, 155795. | Publication | FY2025 |
| Salvato, D., Nguyen, B.-P., Wang, Y., Di Lemma, F. G., Capriotti, L., Aitkaliyeva, A. & T. Yao, (2025). TEM Characterization of Two Variants of Fuel Cladding Chemical Interaction in a HT-9 Clad U-10Zr Fuel. Variant 1: FCCI with a Zr Rind. Journal of Nuclear Materials, 614, 155855. | Publication | FY2025 |
| Espersen, J. I., Garrison, B. E., Cervenka, P., Seshadri, A., Linton, K., Shirvan, K., Capps N.A & N.R. Brown (2025). The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions. Journal of Nuclear Materials, 155910. | Publication | FY2025 |
| Skerjanc, W. F., Jiang, W., Demkowicz, P. A. & J.D. Stempien (2025). Evaluation of AGR-3/4 In-pile Silver Release Predictions Against Post-irradiation Examination measurements. Journal of Nuclear Materials, 615, 155942. | Publication | FY2025 |
| Mauseth, T., Dunzik-Gougar, M. L. & F. Teng (2025). Micro-tensile Characteristics of As-fabricated and Irradiated AGR-2 TRISO Fuel Particle Buffer, IPyC, and Buffer-IPyC Interlayer Regions. Journal of Nuclear Materials, 156086. | Publication | FY2025 |
| Capriotti, L., Di Lemma, F., Salvato, D., Xu, F., Tang, Y., Paaren, K.M., Swearingen, A.L., Jensen, C.B., Wang, Y. & D.L. Porter (2025). An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in HT9/U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis. Journal of Nuclear Materials, p.156092. | Publication | FY2025 |
| Pradhan A, Xu F, Salvato D, et al. (2024). Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning. Mater Charact. 2024;218(1):114524. | Publication | FY2025 |
| Rittenhouse J., Pradhan A., Kamerman D.W, Burns J., Xu F., Wen H. & T. Yao (2025) Site-specific Nanoscale Characterization of Zirconium Hydrides in the Hydride Rim Structure of Hydrogen-charged Zircaloy-4 Cladding. Mater Charact ;224:115006. | Publication | FY2025 |
| Yang, G., Nguyen, B.-P., Rittenhouse, J. E., Xu, F., Gonderman, S., Gazza, J., Xu, P. & T.Yao (2025). Investigating Grain Structure and Microcracking in SiCf-SiCm Composites Using 4D-STEM. Materials Characterization, 225, 115165. | Publication | FY2025 |
| Zhao, L., Xu, F., Porter, D. L. & Y. Wang (2025). Quantification of line dislocations in FFTF irradiated HT9 cladding by deep learning method. Materials Characterization, 227, 115322. | Publication | FY2025 |
| Beausoleil, G. L., Curnutt, B., Moorehead, M. & Bascom, A. (2025). Multi-principal element alloys for fast reactor cladding applications. Nuclear Engineering and Technology, 57(4), 103303. | Publication | FY2025 |
| Chuirazzi, W., Bush, J., Gross, B., Bryant, M., Clark, K., Cook, M., Burtenshaw, J., Price, J., Morankar, S., Blattner, M., Landon, R., Galloway, K., Stanger, J., Stamos, R., Duke, J., Watt, C. & J. Stempien (2025). Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel. Nuclear Engineering and Technology, 57(10), 103726. | Publication | FY2025 |
| Seo S., Folsom C., Jensen C. et al. (2024). International Fuel Performance Study of Fresh Fuel Experiments for PCMI Effects During RIA Experiments. Nuclear Engineering and Design; 430:113673. | Publication | FY2025 |
| Moussaoui, M. A., Anderson, K. S., Yoo, J., & N.E. Woolstenhulme (2025) Device for steam cladding oxidation testing at TREAT, Nuclear Engineering and Design, 445, 114441. | Publication | FY2025 |
| Downey C.M., Oldham N., Fleming A., Chapman D., Mata Cruz A. & K. Ellis (2024). Design of a First-of-a-kind Instrumented Advanced Test Reactor Irradiation Capsule Experiment for in Situ Thermal Conductivity Measurements of Metallic Fuel. Prog Nucl Energy.;175:105325. | Publication | FY2025 |
| Umretiya, R.V, Qu, H., Yin, L., Jurewicz, T.B., Gupta, V.K., Drobnjak, M., Knussman, M. Hoffman, A.K. & R.B. Rebak (2024). Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments, npj Mater Degrad 8, 88. | Publication | FY2025 |
| Zhao, L., Wang, Y., & F. Xu (2025). Accurate Segmentation of Localized Fuel Cladding Chemical Interaction Layers in SEM Micrographs with Deep Learning Method. Scientific Reports, 15, 28878. | Publication | FY2025 |
| Chavez, R., Anand, N.K. & Hassan, Y. & S. Girimaji (2024) "Flow Over a Sphere at Elevated Pressures: An Analysis of the Near-Wake Using Spectral Proper Orthogonal Decomposition" Physics of Fluids, November 2024, Vol. 36, 115155 (1-17) Issue 11, selected as Editors Pick. | Publication | FY2025 |
| Hawkes, G., Pham, B. & C. Otani (2024). Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps. Nuclear Science and Engineering, 126. | Publication | FY2025 |
| Riet, A. A. & J.D. Stempien (2025). Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation. Nuclear Science and Engineering, 112. | Publication | FY2025 |
| Petersen, P. G., Hansen, R. S., Cappia, F., Kamerman, D., Baird, K. & C. Christensen (2024). Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens. Journal of Testing and Evaluation, 52(6), 33263345. | Publication | FY2025 |
| Capps, N., Yan, Y., Harp, J., Ridley, M. & R. Salko Jr. (2024). Recent High Burnup LOCA Testing at Oak Ridge National Laboratory (ORNL/SPR-2024/3544). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Singh G., Yu J., Xu F., Yao T. & P. Xu (2024). Multiscale Modeling of Silicon Carbide Cladding for Nuclear Applications: Thermal Performance Modeling. Energies. 2024; 17(23):6124. | Publication | FY2025 |
| Cakmak, E., Cinbiz, M. N., Arregui-Mena, J. D., Deck, C. & T. Koyanagi (2025). Damage Progression and Failure of SiC/SiC Composite Tubes under Hard-Contact Radial Expansion. Composites Part B: Engineering, 112869. | Publication | FY2025 |
| Dolley, E. J., Zhang, W., Zorn, G., Sand, T. & R.B. Rebak (2024) "Enhanced mechanical properties and wear resistance of FeCrAl alloys at~ 300 C and Higher temperatures." JOM 76, no. 8 (2024): 4123-4130. | Publication | FY2025 |
| Nagothi, B.S., Qu, H., Zhang, W., Umretiya, R.V., Dolley, E.& R.B. Rebak (2024). "Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding." Materials 17, no. 7: 1633. | Publication | FY2025 |
| Qu, H., Yin, L., Larsen, M., and R.B. Rebak (2024). "Distinctive oxide films develop on the surface of fecral as the environment changes for nuclear fuel cladding." Corrosion and Materials Degradation 5, no. 1: 109-123. | Publication | FY2025 |
| Woolstenhulme, N. et al. (2025). SPARC - Plans for a New Critical Experiment Facility with a Horizontal Split Table (INL/RPT-25-84855). Idaho National Laboratory, Idaho Falls, ID. | Publication | FY2025 |
| Yang, Y., Weicheng Z. & C. Massey (2025). Computational Design of Improved Fast Reactor Cladding (ORNL/TM-2025/3953), Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., Laug, D.V. & J.D. Stempien (2024). Micro-tensile Properties of Fueled Irradiated AGR-2 TRISO-coated Particle Buffer, IPyC, and SiC Interlayer Regions. Presented at the 2024 Nuclear Materials (NuMat) Conference. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L. & J.D. Stempien (2024). Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., & J.D. Stempien (2024). Fracture Behavior Considerations for the TRISO Particle Matrix. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles. Presented at the 2025 Nuclear Science User Facilities (NSUF) Annual Program Review. | Publication | FY2025 |
| Qu, H.J., Chikhalikar, A.S., Abouelella, H., Roy, I., Rajendran, R., Nagothi, B.S., Umretiya, R., Hoffman, A.K. & R.B. Rebak (2024). "Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments." Corrosion Science 229 (2024): 111870. | Publication | FY2025 |
| Roy, R., Chatterjee, A., Mondal, S., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya.(2025). "Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions." Corrosion Science: 112965. | Publication | FY2025 |
| Mondal, S., Chatterjee, A., Roy, R., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya. "Synergistic Roles of Cr and Mo in Low Temperature Steam Oxidation of FeCrAl Alloys." Corrosion Science (2025): 113107. | Publication | FY2025 |
| Rajendran, R., Chikhalikar, A.S., Roy, I., Abouelella, H., Qu, H.J., Umretiya, R.V., Hoffman, A.K., and R.B. Rebak (2024). "Effect of aging and ?segregation on oxidation and electrochemical behavior of FeCrAl alloys." Journal of Nuclear Materials 588: 154751. | Publication | FY2025 |
| Joyce, L., Wang, P., Umretiya, R.V., Hoffman, A. & Y. Xie (2024). "Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water." Journal of Nuclear Materials 593: 154987. | Publication | FY2025 |
| Chikhalikar, A.S., Qu, H., Abouelella, H., Nagothi, B., Rajendran, R., Roy, I., Umretiya, R., Hoffman, A. & R. Rebak, . "Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys." Journal of Nuclear Materials 598 (2024): 155179. | Publication | FY2025 |
| Nelson M., Samuha S., Kombaiah B., Kamerman D. & P. Hosemann (2024). Enhanced Stress Relaxation Behavior Via Basal ?a?dislocation activity in Zircaloy-4 cladding. Journal of Nuclear Materials ;601:155337. | Publication | FY2025 |
| Hirschhorn J.A., Aagesen L.K., Jiang C. & G.L. Beausoleil (2025). Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nucl Eng Des ;432:113811. | Publication | FY2025 |
| Ravi, S.K., Comlek, Y., Pathak, A., Gupta, V., Umretiya, R., Hoffman, A., Pilania, G. et al. (2025) "Interpretable multi-source data fusion through Latent Variable Gaussian Process." Engineering Applications of Artificial Intelligence 145: 110033. | Publication | FY2025 |
| Umretiya, R.V., Chikhalikar, A., Elward, B., Moreira, T.A., Anderson, M., Rebak, R.B. & J.V. Rojas (2024). "The Effect of Ramp Heating on the Microstructure and Surface Chemistry of APMT FeCrAl Alloy." Nuclear Materials and Energy 38: 101567. | Publication | FY2025 |
| Joyce, L., Umretiya, R.V., Qu, H., Shang, Z. & Y. Xie (2025). "Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400900° C." Nuclear Materials and Energy : 101953. | Publication | FY2025 |
| Bermudez, S., Erdogan, F., Davis, V., Rojas, J.V. & R.V. Umretiya (2025). "Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000° C)." Nuclear Materials and Energy : 101972. | Publication | FY2025 |
| Bawane, K.K., Yang, G., Yao, T., Xu, F., Xu, P., Gonderman, S. & J. Gazza (2025). Microstructure Analysis of Silicon Carbide Cladding Using 4D-STEM. Paper presented at M&M 2025. | FY2025 | |
| Cappia F., Colldeweih, A., Frazer, D., Hansen, R., Petersen, P., Stockwell, J., Anderson, S., Charbeneau, J., Kamerman, D. (2024) Effect of Metal Contaminants on Cr Coating Performance after Irradiation in the Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Carvajal, J. (2025). In-Rod Sensor System Irradiation Test Results with Segmented Fuel Assembly, accepted for the 14th International Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2025), Chicago. | FY2025 | |
| Cervenka, P., Seshadri A., Sevecek M., Cvrcek L. & K. Shirvan (2024). Development of PVD Cr-(Nb) coated fuel cladding with enhanced accident tolerance, Presented at the Nuclear Materials Conference. | FY2025 | |
| Chavez, R. (2025). Fluid Dynamics and Thermal Effects of Flow Over a Sphere at High Pressures and Graphitic Dust Behavior in Square Channels, PhD Dissertation, Texas A&M University. | FY2025 | |
| Chavez, R., Anand, N.K. & Y. Hassan (2025) High-Pressure Experimental Analysis of Thermal Effects on Near-Wake Turbulence and Energy Distribution of Flow over a Heated Sphere, Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Colldeweih A., Kamerman, D., Matos, M., Bawane, K., J. Stockwell, J., A. Pradhan, A., Hansen, R., Cappia, F. & D. Lutz (2024) Corrosion of Neutron Irradiated FeCrAl in the ATR Water Loop TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Dabney, T., Sasidhar, K.N., Willing, E., Eftink, B., Li, N., Maier, B., Walters, J. & K. Sridharan (2025). Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding, Symposium on Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Hansen R., Colldeweih, A., Petersen, P., Stockwell, J., Charboneau, J., Albuquerque, L., Baird, K., Kamerman, D. & F. Cappia (2024) Examinations of Cr-Coated M5 Cladding Irradiated at the INL Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Harp, J., Yan, Y., Morris, R., Baldwin, C., Jones, M. & N. Capps (2024). Development of Fission Gas Release Cabilities to Study High Burnup Commercial Fuel Performance under Loss of Coolant Accident Conditions. Proc. TopFuel 2024, Grenoble, France. | FY2025 | |
| Jung, W., Dunbar, C., Jo, J.Y., Sridharan, K. & H. Yeom (2025). Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr cladding under Multiple Quench Tests, Symposium on Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Karlsson, T. Y. (2025). Fuel Qualification: Near-Term Activities & Needs for Molten Salt Fuels. Presented at the EPRI Advanced Reactor Workshop. | FY2025 | |
| Kosmidou, M., Broussard, A., Lian, J. & E. Kardoulaki (2025). Filling of data gaps for the development of ceramic fuels, pp. 23.Materials in Nuclear Energy Systems (MiNES) 2025 Conference. | FY2025 | |
| Li, N., Xie, D., Kim, H., Dabney, T., Eftink, B., Sridharan, K., Graening, T., Nelson, A., Fensin, S.& S. Maloy (2025). In Situ Micro-Cantilever Beam Bending Tests to Assess the Adhesion Strength of Cr Coatings on Zry-4, Symposium on Mechanical Behavior Related to Interface Physics IV, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Microstructural Characterization of AGR-2 TRISO Particle Buffer, IPyC, and Buffer-IPyC Interfaces. Presented at the 2025 Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). | FY2025 | |
| Pham, B. T., Hawkes, G. L., Lybeck, N. J., Otani, C. & P.A. Demkowicz (2025). Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment. Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Seshadri A., Cervenka P., Fazi A., Sevecek M., Carpenter D., Cetiner N., Motta A., Ishak C., Fei Z., Raiman S., Xu P. & K. Shirvan. In-pile hydrothermal corrosion behavior of Zirconium Alloys with and without ATF Coatings, Presented at 21st ASTM International Symposium on Zirconium in the Nuclear Industry. | FY2025 | |
| Shirvan K., Cervenka P., Fazi A. & A. Seshadri (2025). Experimental Investigation of CrNb Coatings for PWRs and BWRs. Paper at the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. | FY2025 | |
| Sridharan, K. Maier, B., Dabney, T., Willing, E., Pocquette, N. Lukas, C., Anderson, N. & H. Yeom (2025). Cold Spray Materials Deposition Technology for Nuclear Energy Systems, Symposium on Advances in Materials Deposition by Cold Spray and Related Technologies, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Walter, J., Roberts, E., Fredrick, K., Viands, D. & X. Huang (2025). The Effect of Chromium Coating Microstructure and Oxide Films on Hydrogen Uptake in Zirconium-alloy Nuclear Fuel Cladding, 21st International Symposium on Zirconium in the Nuclear Industry, Aix-en-Provence, France. | FY2025 | |
| Woolstenhulme, N., Martin, N., DeHart, M., Percher, C., Cutler, T., Wieselquist, W. (2025). SPARC, an Effort to Reestablish a Horizontal Split Table Critical Facility for HALEU Experiments and Beyond. Paper presented at the NCSD 2025 Annual Meeting. | FY2025 | |
| Yuan, G., Cook, D.H., Barnard, H., Lahoda, E., Xu, P., Ritchie, R.O. & D. Liu (2025). Improved Damage Tolerance of SiC-Based Nuclear Fuel Cladding with Novel Multi-Layered SiC Coating Design at 1200°C, Materials & Design, Volume 256, August 2025, 114260. | Publication | FY2025 |
| Zhang, S., Ma, Z., Xu, P. (2024). Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors, 2024 ANS Annual Meeting. | FY2025 | |
| Zhang, J., Xu, P., Sevecek, M., Sim, K.S. & A. Khaperskaia (2025). Contribution of IAEA Coordinated Research Projects to Light Water Reactors Advanced Technology Fuel Testing and Simulation, Nuclear Engineering and Design 418, 112910. | Publication | FY2025 |
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | FY2016 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | FY2016 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | FY2016 | |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | FY2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | FY2016 |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | FY2016 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | FY2016 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | FY2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | FY2016 | |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OÂBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | FY2016 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | FY2016 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | FY2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | FY2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | FY2016 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | FY2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | FY2016 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | FY2016 | |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | FY2016 | |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | FY2016 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | FY2016 | |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | FY2016 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | FY2016 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | FY2016 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | FY2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | FY2016 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | FY2016 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | FY2016 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | FY2016 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Cole, J. I., T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | FY2010 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | FY2016 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | FY2016 | |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | FY2016 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OÂBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | FY2016 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | FY2016 | |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | FY2016 | |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | FY2016 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | FY2016 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | FY2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | FY2011 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | FY2016 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(1-3), 2-7. | Publication | FY2011 |
| OÂBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | FY2016 | |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | FY2016 |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| Cole, J. I., O'Holleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | FY2011 | |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | FY2016 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Hurley, D. H., Khafizov, M., Shinde, S., Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | FY2011 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Janney, D. E., Kennedy, J. R. (2010). As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | FY2011 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | FY2016 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | FY2016 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | FY2016 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., Sohn, Y. H. (2011). Thermotransport in γ(bcc) U-Zr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | FY2011 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | FY2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | FY2016 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | FY2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | FY2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | FY2016 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | FY2016 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | FY2016 | |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | FY2016 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | FY2016 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | FY2016 | |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | FY2016 |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | FY2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | FY2016 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | FY2016 | |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | FY2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | FY2016 | |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | FY2016 | |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Mariani, R. D., Porter, D. L., O'Holleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | FY2012 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | FY2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | FY2016 | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | FY2016 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | FY2016 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | FY2016 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | FY2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 2089-2107. | Publication | FY2013 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | FY2016 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | FY2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | FY2016 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(1-3), 1-8. | Publication | FY2013 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | FY2016 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of U-Pu-Zr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | FY2013 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | FY2017 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | FY2017 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | FY2017 | |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | FY2017 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | FY2017 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417-428. | Publication | FY2013 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I-Mechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | FY2013 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II- Mechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | FY2013 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155-163. | Publication | FY2013 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | FY2017 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | FY2017 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1-yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | FY2013 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | FY2017 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgO-Nd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | FY2013 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | FY2017 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Park, Y., Huang, K., Paz y Puente, A., et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 72-82. | Publication | FY2013 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145-154. | Publication | FY2013 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | FY2017 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | FY2013 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | FY2017 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF. Journal of Nuclear Materials, 428(1-3), 170-175. | Publication | FY2013 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | FY2017 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems  Water Reactors. | Publication | FY2017 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | FY2017 | |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9-y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | FY2013 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | FY2017 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | FY2017 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(1-3), 206-213. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | FY2017 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | FY2017 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | FY2017 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | FY2017 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | FY2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | FY2017 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 - The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | FY2014 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | FY2017 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(1-3), 263-272. | Publication | FY2014 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | FY2017 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(1-3), 290-299. | Publication | FY2014 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(1-3), 39-48. | Publication | FY2014 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | FY2017 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | FY2017 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction. Journal of Nuclear Materials, 448(1-3), 534-540. | Publication | FY2014 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | FY2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238-251. | Publication | FY2014 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | FY2017 | |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | FY2017 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(1-3), 162-167. | Publication | FY2014 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(1-3), 497-511. | Publication | FY2014 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | FY2017 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | FY2017 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(1-3), 441-447. | Publication | FY2014 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | FY2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(1-3), 520-533. | Publication | FY2014 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 14-17, 2014. | Publication | FY2014 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | FY2017 | |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh,; J. Mat (Eds.), Ceramic Materials for Energy Applications IV. | Publication | FY2014 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | FY2017 | |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | FY2017 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | FY2017 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(1-3), 323-333. | Publication | FY2014 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | FY2017 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | FY2017 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | FY2017 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(1-3), 304-310. | Publication | FY2014 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | FY2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2-MgAl2O4-CeMgAl11O19) and four-phase (3Y-TZP-Al2O3-MgAl2O4-LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | FY2015 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | FY2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | FY2017 | |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | FY2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | FY2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | FY2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., O'Brien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | FY2015 | |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | FY2017 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-Y-O system. Journal of Nuclear Materials, 460, 5-12. | Publication | FY2015 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | FY2017 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | FY2017 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UN-U3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | FY2015 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | FY2017 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system - FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | FY2015 | |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | FY2017 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | FY2017 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | FY2015 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | FY2018 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523-537. | Publication | FY2015 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | FY2018 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | FY2018 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | FY2018 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | FY2018 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | FY2018 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | FY2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | FY2018 | |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | FY2018 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | FY2018 | |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 15-21, 2013. ASME. | Publication | FY2015 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | FY2018 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ~295 °C to ~6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | FY2015 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | FY2018 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-La-O system. Journal of Nuclear Materials, 456, 142-150. | Publication | FY2015 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | FY2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | FY2018 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 13-17, 2014 | Publication | FY2015 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | FY2018 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Robb, K. R., & Powers, J. J. (2014, October 27-30). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | FY2015 | |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | FY2018 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | FY2018 | |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | FY2018 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | FY2018 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 670-1498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | FY2015 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | FY2018 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | FY2018 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | FY2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b, INL/EXT-14-33641, Rev 0, November 2014. | FY2015 | |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | FY2018 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., O'Brien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | FY2015 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | FY2018 | |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | FY2016 | |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | FY2018 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | FY2018 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | FY2018 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Âeve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold sprayÂcoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | FY2018 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | FY2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | FY2018 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | FY2018 | |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | FY2018 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | FY2018 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | FY2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxideÂsilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | FY2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | FY2016 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | FY2019 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | FY2019 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | FY2019 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | FY2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | FY2019 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | FY2019 |
| Publication | ||
| Publication | ||
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | FY2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | FY2019 | |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | FY2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | FY2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | FY2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) Â A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | FY2019 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | FY2019 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 1-5, 2016 | Publication | FY2016 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | FY2019 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | FY2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | FY2019 | |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 1703Â1709. | Publication | FY2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | FY2019 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., O'Brien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | FY2019 | |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., O'Brien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | FY2016 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | FY2019 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | FY2016 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | FY2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | FY2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | FY2019 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program - current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | FY2016 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | FY2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | FY2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | FY2019 | |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | FY2016 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | FY2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | FY2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | FY2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | FY2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | FY2019 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | FY2019 | |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | FY2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | FY2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | FY2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | FY2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 17-20, 2016. | Publication | FY2016 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | FY2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | FY2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | FY2019 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 17-21, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | FY2016 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | FY2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | FY2019 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | FY2019 | |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | FY2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | FY2019 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | FY2019 | |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | FY2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | FY2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | FY2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | FY2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | FY2019 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | FY2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | FY2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | FY2019 |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | FY2019 | |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | FY2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | FY2019 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O'Brien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1-5, 2016. | FY2016 | |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | FY2016 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | FY2017 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA's Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea, September 2017 | FY2017 | |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on "In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures". Journal of Nuclear Materials, 484, 168-173. | Publication | FY2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | FY2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 1475-1483). | Publication | FY2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDE-pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | FY2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1-x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | FY2017 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 6429-6434. | Publication | FY2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176-185. | Publication | FY2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 1484-1492. | Publication | FY2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 1373-1382. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™. Journal of Nuclear Materials, 507, 306-315. | Publication | FY2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269-272. | Publication | FY2018 |
| Kilby S.M, Marshall M.A, Choe D.O. et al. (2024). Design of Mini-Plate-1 Irradiation Test for Qualification of High-Density, Low-Enriched U-10Mo Monolithic Fuel. JOM. | Publication | FY2025 |
| Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C. & M. Tippet (2024). Fast Neutron Irradiation Capability in Existing Thermal Test Reactors, Annals of Nuclear Energy, Volume 207, 110731, ISSN 0306-4549. | Publication | FY2025 |
| Wang, Y., Burns, J., Yao, T. & L. Capriotti (2024). Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155209, ISSN 0022-3115. | Publication | FY2025 |
| Wang, Y., Howard, C., Xu, F., Salvato, D., Bawane, K., Murray, D., Frazer, D., Anderson, S., Yao, T., Yeo, S., Kim, J-H, Lee, B-O, Kim, J., Fielding, R. & L. Capriotti (2024). Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155231, ISSN 0022-3115. | Publication | FY2025 |
| Nicodemo G., Zullo G., Cappia F., Van Uffelen P., De Lara A., Luzzi L. & D. Pizzocri (2024). Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity. Journal of Nuclear Materials. 601:155301. | Publication | FY2025 |
| Colldeweih A., P. Petersen, M. Matos, J. Stockwell, R. Hansen, D. Kamerman, D. Lutz & F. Cappia (2025) Post irradiation examinations of FeCrAl cladding in PWR conditions Journal of Nuclear Materials Vol. 603, 155402 | Publication | FY2025 |
| Dabney, T., Sasidhar, K.N., Willing, E., Lukas, C., Quillin, K., Yeon, H. & K. Sridharan (2025). Microstructural Evolution in Ion Irradiated Cold Spray Cr Coated Zr-alloy, Journal of Nuclear Materials, vol. 606, 155652 | Publication | FY2025 |
| Chen, D., Burns, J., Wright, K. E., Salvato, D., Yao, T. & L. Capriotti (2025). Transmission electron microscopy characterization of fuel cladding chemical interaction between minor actinides bearing U-Pu-Zr fuel and AIM1 cladding. Journal of Nuclear Materials, 607, 155667. | Publication | FY2025 |
| Kancharla R.R, Chuirazzi W.C, Kane J.J et al. (2025). X-ray computed tomography of deconsolidated TRISO particles from the AGR-5/6/7 irradiation experiment capsule 1 compact. J Nucl Mater. ; 607:155704. doi:10.1016/j.jnucmat.2025.155704. | Publication | FY2025 |
| Meehan N.A., Gorton J.P., Capps N.A. & N.R. Brown (2025). Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions. Journal of Nuclear Materials, 2025;609:155745. doi:10.1016/j.jnucmat.155745. | Publication | FY2025 |
| Middlemas, S., & C. Adkins (2025). A critical analysis of U-Pu-Zr phase transitions using calorimetric, microstructural, and phase equilibria data. Journal of Nuclear Materials, 612, 155778. | Publication | FY2025 |
| Probert A., Swearingen A., Schulthess J., Capriotti L., Jensen C. & A. Aitkaliyeva (2025). Comparative Post-irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Steady-state Irradiation Behavior Against Historical and Modeled Fuel Performance. Journal of Nuclear Materials.; 610:155782. | Publication | FY2025 |
| Dhulipala, S. L. N., Simon, P.-C. A., Demkowicz, P. A., Hirschhorn, J. A. & S. R. Novascone (2025). Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches. Journal of Nuclear Materials, 610, 155795. | Publication | FY2025 |
| Salvato, D., Nguyen, B.-P., Wang, Y., Di Lemma, F. G., Capriotti, L., Aitkaliyeva, A. & T. Yao, (2025). TEM Characterization of Two Variants of Fuel Cladding Chemical Interaction in a HT-9 Clad U-10Zr Fuel. Variant 1: FCCI with a Zr Rind. Journal of Nuclear Materials, 614, 155855. | Publication | FY2025 |
| Espersen, J. I., Garrison, B. E., Cervenka, P., Seshadri, A., Linton, K., Shirvan, K., Capps N.A & N.R. Brown (2025). The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions. Journal of Nuclear Materials, 155910. | Publication | FY2025 |
| Skerjanc, W. F., Jiang, W., Demkowicz, P. A. & J.D. Stempien (2025). Evaluation of AGR-3/4 In-pile Silver Release Predictions Against Post-irradiation Examination measurements. Journal of Nuclear Materials, 615, 155942. | Publication | FY2025 |
| Mauseth, T., Dunzik-Gougar, M. L. & F. Teng (2025). Micro-tensile Characteristics of As-fabricated and Irradiated AGR-2 TRISO Fuel Particle Buffer, IPyC, and Buffer-IPyC Interlayer Regions. Journal of Nuclear Materials, 156086. | Publication | FY2025 |
| Capriotti, L., Di Lemma, F., Salvato, D., Xu, F., Tang, Y., Paaren, K.M., Swearingen, A.L., Jensen, C.B., Wang, Y. & D.L. Porter (2025). An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in HT9/U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis. Journal of Nuclear Materials, p.156092. | Publication | FY2025 |
| Pradhan A, Xu F, Salvato D, et al. (2024). Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning. Mater Charact. 2024;218(1):114524. | Publication | FY2025 |
| Rittenhouse J., Pradhan A., Kamerman D.W, Burns J., Xu F., Wen H. & T. Yao (2025) Site-specific Nanoscale Characterization of Zirconium Hydrides in the Hydride Rim Structure of Hydrogen-charged Zircaloy-4 Cladding. Mater Charact ;224:115006. | Publication | FY2025 |
| Yang, G., Nguyen, B.-P., Rittenhouse, J. E., Xu, F., Gonderman, S., Gazza, J., Xu, P. & T.Yao (2025). Investigating Grain Structure and Microcracking in SiCf-SiCm Composites Using 4D-STEM. Materials Characterization, 225, 115165. | Publication | FY2025 |
| Zhao, L., Xu, F., Porter, D. L. & Y. Wang (2025). Quantification of line dislocations in FFTF irradiated HT9 cladding by deep learning method. Materials Characterization, 227, 115322. | Publication | FY2025 |
| Beausoleil, G. L., Curnutt, B., Moorehead, M. & Bascom, A. (2025). Multi-principal element alloys for fast reactor cladding applications. Nuclear Engineering and Technology, 57(4), 103303. | Publication | FY2025 |
| Chuirazzi, W., Bush, J., Gross, B., Bryant, M., Clark, K., Cook, M., Burtenshaw, J., Price, J., Morankar, S., Blattner, M., Landon, R., Galloway, K., Stanger, J., Stamos, R., Duke, J., Watt, C. & J. Stempien (2025). Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel. Nuclear Engineering and Technology, 57(10), 103726. | Publication | FY2025 |
| Seo S., Folsom C., Jensen C. et al. (2024). International Fuel Performance Study of Fresh Fuel Experiments for PCMI Effects During RIA Experiments. Nuclear Engineering and Design; 430:113673. | Publication | FY2025 |
| Moussaoui, M. A., Anderson, K. S., Yoo, J., & N.E. Woolstenhulme (2025) Device for steam cladding oxidation testing at TREAT, Nuclear Engineering and Design, 445, 114441. | Publication | FY2025 |
| Downey C.M., Oldham N., Fleming A., Chapman D., Mata Cruz A. & K. Ellis (2024). Design of a First-of-a-kind Instrumented Advanced Test Reactor Irradiation Capsule Experiment for in Situ Thermal Conductivity Measurements of Metallic Fuel. Prog Nucl Energy.;175:105325. | Publication | FY2025 |
| Umretiya, R.V, Qu, H., Yin, L., Jurewicz, T.B., Gupta, V.K., Drobnjak, M., Knussman, M. Hoffman, A.K. & R.B. Rebak (2024). Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments, npj Mater Degrad 8, 88. | Publication | FY2025 |
| Zhao, L., Wang, Y., & F. Xu (2025). Accurate Segmentation of Localized Fuel Cladding Chemical Interaction Layers in SEM Micrographs with Deep Learning Method. Scientific Reports, 15, 28878. | Publication | FY2025 |
| Chavez, R., Anand, N.K. & Hassan, Y. & S. Girimaji (2024) "Flow Over a Sphere at Elevated Pressures: An Analysis of the Near-Wake Using Spectral Proper Orthogonal Decomposition" Physics of Fluids, November 2024, Vol. 36, 115155 (1-17) Issue 11, selected as Editors Pick. | Publication | FY2025 |
| Hawkes, G., Pham, B. & C. Otani (2024). Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps. Nuclear Science and Engineering, 126. | Publication | FY2025 |
| Riet, A. A. & J.D. Stempien (2025). Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation. Nuclear Science and Engineering, 112. | Publication | FY2025 |
| Petersen, P. G., Hansen, R. S., Cappia, F., Kamerman, D., Baird, K. & C. Christensen (2024). Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens. Journal of Testing and Evaluation, 52(6), 33263345. | Publication | FY2025 |
| Capps, N., Yan, Y., Harp, J., Ridley, M. & R. Salko Jr. (2024). Recent High Burnup LOCA Testing at Oak Ridge National Laboratory (ORNL/SPR-2024/3544). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Singh G., Yu J., Xu F., Yao T. & P. Xu (2024). Multiscale Modeling of Silicon Carbide Cladding for Nuclear Applications: Thermal Performance Modeling. Energies. 2024; 17(23):6124. | Publication | FY2025 |
| Cakmak, E., Cinbiz, M. N., Arregui-Mena, J. D., Deck, C. & T. Koyanagi (2025). Damage Progression and Failure of SiC/SiC Composite Tubes under Hard-Contact Radial Expansion. Composites Part B: Engineering, 112869. | Publication | FY2025 |
| Dolley, E. J., Zhang, W., Zorn, G., Sand, T. & R.B. Rebak (2024) "Enhanced mechanical properties and wear resistance of FeCrAl alloys at~ 300 C and Higher temperatures." JOM 76, no. 8 (2024): 4123-4130. | Publication | FY2025 |
| Nagothi, B.S., Qu, H., Zhang, W., Umretiya, R.V., Dolley, E.& R.B. Rebak (2024). "Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding." Materials 17, no. 7: 1633. | Publication | FY2025 |
| Qu, H., Yin, L., Larsen, M., and R.B. Rebak (2024). "Distinctive oxide films develop on the surface of fecral as the environment changes for nuclear fuel cladding." Corrosion and Materials Degradation 5, no. 1: 109-123. | Publication | FY2025 |
| Woolstenhulme, N. et al. (2025). SPARC - Plans for a New Critical Experiment Facility with a Horizontal Split Table (INL/RPT-25-84855). Idaho National Laboratory, Idaho Falls, ID. | Publication | FY2025 |
| Yang, Y., Weicheng Z. & C. Massey (2025). Computational Design of Improved Fast Reactor Cladding (ORNL/TM-2025/3953), Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., Laug, D.V. & J.D. Stempien (2024). Micro-tensile Properties of Fueled Irradiated AGR-2 TRISO-coated Particle Buffer, IPyC, and SiC Interlayer Regions. Presented at the 2024 Nuclear Materials (NuMat) Conference. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L. & J.D. Stempien (2024). Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., & J.D. Stempien (2024). Fracture Behavior Considerations for the TRISO Particle Matrix. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles. Presented at the 2025 Nuclear Science User Facilities (NSUF) Annual Program Review. | Publication | FY2025 |
| Qu, H.J., Chikhalikar, A.S., Abouelella, H., Roy, I., Rajendran, R., Nagothi, B.S., Umretiya, R., Hoffman, A.K. & R.B. Rebak (2024). "Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments." Corrosion Science 229 (2024): 111870. | Publication | FY2025 |
| Roy, R., Chatterjee, A., Mondal, S., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya.(2025). "Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions." Corrosion Science: 112965. | Publication | FY2025 |
| Mondal, S., Chatterjee, A., Roy, R., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya. "Synergistic Roles of Cr and Mo in Low Temperature Steam Oxidation of FeCrAl Alloys." Corrosion Science (2025): 113107. | Publication | FY2025 |
| Rajendran, R., Chikhalikar, A.S., Roy, I., Abouelella, H., Qu, H.J., Umretiya, R.V., Hoffman, A.K., and R.B. Rebak (2024). "Effect of aging and ?segregation on oxidation and electrochemical behavior of FeCrAl alloys." Journal of Nuclear Materials 588: 154751. | Publication | FY2025 |
| Joyce, L., Wang, P., Umretiya, R.V., Hoffman, A. & Y. Xie (2024). "Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water." Journal of Nuclear Materials 593: 154987. | Publication | FY2025 |
| Chikhalikar, A.S., Qu, H., Abouelella, H., Nagothi, B., Rajendran, R., Roy, I., Umretiya, R., Hoffman, A. & R. Rebak, . "Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys." Journal of Nuclear Materials 598 (2024): 155179. | Publication | FY2025 |
| Nelson M., Samuha S., Kombaiah B., Kamerman D. & P. Hosemann (2024). Enhanced Stress Relaxation Behavior Via Basal ?a?dislocation activity in Zircaloy-4 cladding. Journal of Nuclear Materials ;601:155337. | Publication | FY2025 |
| Hirschhorn J.A., Aagesen L.K., Jiang C. & G.L. Beausoleil (2025). Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nucl Eng Des ;432:113811. | Publication | FY2025 |
| Ravi, S.K., Comlek, Y., Pathak, A., Gupta, V., Umretiya, R., Hoffman, A., Pilania, G. et al. (2025) "Interpretable multi-source data fusion through Latent Variable Gaussian Process." Engineering Applications of Artificial Intelligence 145: 110033. | Publication | FY2025 |
| Umretiya, R.V., Chikhalikar, A., Elward, B., Moreira, T.A., Anderson, M., Rebak, R.B. & J.V. Rojas (2024). "The Effect of Ramp Heating on the Microstructure and Surface Chemistry of APMT FeCrAl Alloy." Nuclear Materials and Energy 38: 101567. | Publication | FY2025 |
| Joyce, L., Umretiya, R.V., Qu, H., Shang, Z. & Y. Xie (2025). "Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400900° C." Nuclear Materials and Energy : 101953. | Publication | FY2025 |
| Bermudez, S., Erdogan, F., Davis, V., Rojas, J.V. & R.V. Umretiya (2025). "Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000° C)." Nuclear Materials and Energy : 101972. | Publication | FY2025 |
| Bawane, K.K., Yang, G., Yao, T., Xu, F., Xu, P., Gonderman, S. & J. Gazza (2025). Microstructure Analysis of Silicon Carbide Cladding Using 4D-STEM. Paper presented at M&M 2025. | FY2025 | |
| Cappia F., Colldeweih, A., Frazer, D., Hansen, R., Petersen, P., Stockwell, J., Anderson, S., Charbeneau, J., Kamerman, D. (2024) Effect of Metal Contaminants on Cr Coating Performance after Irradiation in the Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Carvajal, J. (2025). In-Rod Sensor System Irradiation Test Results with Segmented Fuel Assembly, accepted for the 14th International Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2025), Chicago. | FY2025 | |
| Cervenka, P., Seshadri A., Sevecek M., Cvrcek L. & K. Shirvan (2024). Development of PVD Cr-(Nb) coated fuel cladding with enhanced accident tolerance, Presented at the Nuclear Materials Conference. | FY2025 | |
| Chavez, R. (2025). Fluid Dynamics and Thermal Effects of Flow Over a Sphere at High Pressures and Graphitic Dust Behavior in Square Channels, PhD Dissertation, Texas A&M University. | FY2025 | |
| Chavez, R., Anand, N.K. & Y. Hassan (2025) High-Pressure Experimental Analysis of Thermal Effects on Near-Wake Turbulence and Energy Distribution of Flow over a Heated Sphere, Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Colldeweih A., Kamerman, D., Matos, M., Bawane, K., J. Stockwell, J., A. Pradhan, A., Hansen, R., Cappia, F. & D. Lutz (2024) Corrosion of Neutron Irradiated FeCrAl in the ATR Water Loop TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Dabney, T., Sasidhar, K.N., Willing, E., Eftink, B., Li, N., Maier, B., Walters, J. & K. Sridharan (2025). Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding, Symposium on Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Hansen R., Colldeweih, A., Petersen, P., Stockwell, J., Charboneau, J., Albuquerque, L., Baird, K., Kamerman, D. & F. Cappia (2024) Examinations of Cr-Coated M5 Cladding Irradiated at the INL Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Harp, J., Yan, Y., Morris, R., Baldwin, C., Jones, M. & N. Capps (2024). Development of Fission Gas Release Cabilities to Study High Burnup Commercial Fuel Performance under Loss of Coolant Accident Conditions. Proc. TopFuel 2024, Grenoble, France. | FY2025 | |
| Jung, W., Dunbar, C., Jo, J.Y., Sridharan, K. & H. Yeom (2025). Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr cladding under Multiple Quench Tests, Symposium on Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Karlsson, T. Y. (2025). Fuel Qualification: Near-Term Activities & Needs for Molten Salt Fuels. Presented at the EPRI Advanced Reactor Workshop. | FY2025 | |
| Kosmidou, M., Broussard, A., Lian, J. & E. Kardoulaki (2025). Filling of data gaps for the development of ceramic fuels, pp. 23.Materials in Nuclear Energy Systems (MiNES) 2025 Conference. | FY2025 | |
| Li, N., Xie, D., Kim, H., Dabney, T., Eftink, B., Sridharan, K., Graening, T., Nelson, A., Fensin, S.& S. Maloy (2025). In Situ Micro-Cantilever Beam Bending Tests to Assess the Adhesion Strength of Cr Coatings on Zry-4, Symposium on Mechanical Behavior Related to Interface Physics IV, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Microstructural Characterization of AGR-2 TRISO Particle Buffer, IPyC, and Buffer-IPyC Interfaces. Presented at the 2025 Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). | FY2025 | |
| Pham, B. T., Hawkes, G. L., Lybeck, N. J., Otani, C. & P.A. Demkowicz (2025). Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment. Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Seshadri A., Cervenka P., Fazi A., Sevecek M., Carpenter D., Cetiner N., Motta A., Ishak C., Fei Z., Raiman S., Xu P. & K. Shirvan. In-pile hydrothermal corrosion behavior of Zirconium Alloys with and without ATF Coatings, Presented at 21st ASTM International Symposium on Zirconium in the Nuclear Industry. | FY2025 | |
| Shirvan K., Cervenka P., Fazi A. & A. Seshadri (2025). Experimental Investigation of CrNb Coatings for PWRs and BWRs. Paper at the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. | FY2025 | |
| Sridharan, K. Maier, B., Dabney, T., Willing, E., Pocquette, N. Lukas, C., Anderson, N. & H. Yeom (2025). Cold Spray Materials Deposition Technology for Nuclear Energy Systems, Symposium on Advances in Materials Deposition by Cold Spray and Related Technologies, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Walter, J., Roberts, E., Fredrick, K., Viands, D. & X. Huang (2025). The Effect of Chromium Coating Microstructure and Oxide Films on Hydrogen Uptake in Zirconium-alloy Nuclear Fuel Cladding, 21st International Symposium on Zirconium in the Nuclear Industry, Aix-en-Provence, France. | FY2025 | |
| Woolstenhulme, N., Martin, N., DeHart, M., Percher, C., Cutler, T., Wieselquist, W. (2025). SPARC, an Effort to Reestablish a Horizontal Split Table Critical Facility for HALEU Experiments and Beyond. Paper presented at the NCSD 2025 Annual Meeting. | FY2025 | |
| Yuan, G., Cook, D.H., Barnard, H., Lahoda, E., Xu, P., Ritchie, R.O. & D. Liu (2025). Improved Damage Tolerance of SiC-Based Nuclear Fuel Cladding with Novel Multi-Layered SiC Coating Design at 1200°C, Materials & Design, Volume 256, August 2025, 114260. | Publication | FY2025 |
| Zhang, S., Ma, Z., Xu, P. (2024). Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors, 2024 ANS Annual Meeting. | FY2025 | |
| Zhang, J., Xu, P., Sevecek, M., Sim, K.S. & A. Khaperskaia (2025). Contribution of IAEA Coordinated Research Projects to Light Water Reactors Advanced Technology Fuel Testing and Simulation, Nuclear Engineering and Design 418, 112910. | Publication | FY2025 |
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | FY2016 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | FY2016 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | FY2016 | |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | FY2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | FY2016 |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | FY2016 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | FY2016 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | FY2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | FY2016 | |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OÂBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | FY2016 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | FY2016 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | FY2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | FY2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | FY2016 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | FY2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | FY2016 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | FY2016 | |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | FY2016 | |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | FY2016 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | FY2016 | |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | FY2016 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | FY2016 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | FY2016 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | FY2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | FY2016 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | FY2016 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | FY2016 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | FY2016 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Cole, J. I., T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | FY2010 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | FY2016 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | FY2016 | |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | FY2016 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OÂBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | FY2016 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | FY2016 | |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | FY2016 | |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | FY2016 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | FY2016 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | FY2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | FY2011 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | FY2016 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(1-3), 2-7. | Publication | FY2011 |
| OÂBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | FY2016 | |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | FY2016 |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| Cole, J. I., O'Holleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | FY2011 | |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | FY2016 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Hurley, D. H., Khafizov, M., Shinde, S., Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | FY2011 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Janney, D. E., Kennedy, J. R. (2010). As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | FY2011 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | FY2016 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | FY2016 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | FY2016 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., Sohn, Y. H. (2011). Thermotransport in γ(bcc) U-Zr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | FY2011 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | FY2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | FY2016 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | FY2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | FY2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | FY2016 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | FY2016 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | FY2016 | |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | FY2016 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | FY2016 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | FY2016 | |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | FY2016 |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | FY2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | FY2016 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | FY2016 | |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | FY2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | FY2016 | |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | FY2016 | |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Mariani, R. D., Porter, D. L., O'Holleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | FY2012 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | FY2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | FY2016 | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | FY2016 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | FY2016 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | FY2016 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | FY2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 2089-2107. | Publication | FY2013 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | FY2016 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | FY2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | FY2016 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(1-3), 1-8. | Publication | FY2013 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | FY2016 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of U-Pu-Zr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | FY2013 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | FY2017 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | FY2017 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | FY2017 | |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | FY2017 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | FY2017 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417-428. | Publication | FY2013 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I-Mechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | FY2013 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II- Mechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | FY2013 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155-163. | Publication | FY2013 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | FY2017 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | FY2017 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1-yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | FY2013 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | FY2017 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgO-Nd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | FY2013 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | FY2017 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Park, Y., Huang, K., Paz y Puente, A., et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 72-82. | Publication | FY2013 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145-154. | Publication | FY2013 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | FY2017 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | FY2013 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | FY2017 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF. Journal of Nuclear Materials, 428(1-3), 170-175. | Publication | FY2013 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | FY2017 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems  Water Reactors. | Publication | FY2017 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | FY2017 | |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9-y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | FY2013 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | FY2017 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | FY2017 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(1-3), 206-213. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | FY2017 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | FY2017 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | FY2017 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | FY2017 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | FY2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | FY2017 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 - The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | FY2014 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | FY2017 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(1-3), 263-272. | Publication | FY2014 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | FY2017 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(1-3), 290-299. | Publication | FY2014 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(1-3), 39-48. | Publication | FY2014 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | FY2017 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | FY2017 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction. Journal of Nuclear Materials, 448(1-3), 534-540. | Publication | FY2014 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | FY2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238-251. | Publication | FY2014 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | FY2017 | |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | FY2017 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(1-3), 162-167. | Publication | FY2014 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(1-3), 497-511. | Publication | FY2014 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | FY2017 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | FY2017 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(1-3), 441-447. | Publication | FY2014 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | FY2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(1-3), 520-533. | Publication | FY2014 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 14-17, 2014. | Publication | FY2014 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | FY2017 | |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh,; J. Mat (Eds.), Ceramic Materials for Energy Applications IV. | Publication | FY2014 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | FY2017 | |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | FY2017 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | FY2017 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(1-3), 323-333. | Publication | FY2014 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | FY2017 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | FY2017 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | FY2017 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(1-3), 304-310. | Publication | FY2014 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | FY2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2-MgAl2O4-CeMgAl11O19) and four-phase (3Y-TZP-Al2O3-MgAl2O4-LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | FY2015 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | FY2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | FY2017 | |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | FY2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | FY2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | FY2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., O'Brien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | FY2015 | |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | FY2017 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-Y-O system. Journal of Nuclear Materials, 460, 5-12. | Publication | FY2015 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | FY2017 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | FY2017 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UN-U3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | FY2015 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | FY2017 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system - FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | FY2015 | |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | FY2017 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | FY2017 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | FY2015 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | FY2018 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523-537. | Publication | FY2015 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | FY2018 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | FY2018 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | FY2018 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | FY2018 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | FY2018 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | FY2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | FY2018 | |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | FY2018 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | FY2018 | |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 15-21, 2013. ASME. | Publication | FY2015 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | FY2018 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ~295 °C to ~6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | FY2015 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | FY2018 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-La-O system. Journal of Nuclear Materials, 456, 142-150. | Publication | FY2015 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | FY2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | FY2018 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 13-17, 2014 | Publication | FY2015 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | FY2018 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Robb, K. R., & Powers, J. J. (2014, October 27-30). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | FY2015 | |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | FY2018 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | FY2018 | |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | FY2018 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | FY2018 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 670-1498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | FY2015 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | FY2018 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | FY2018 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | FY2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b, INL/EXT-14-33641, Rev 0, November 2014. | FY2015 | |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | FY2018 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., O'Brien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | FY2015 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | FY2018 | |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | FY2016 | |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | FY2018 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | FY2018 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | FY2018 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Âeve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold sprayÂcoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | FY2018 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | FY2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | FY2018 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | FY2018 | |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | FY2018 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | FY2018 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | FY2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxideÂsilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | FY2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | FY2016 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | FY2019 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | FY2019 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | FY2019 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | FY2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | FY2019 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | FY2019 |
| Publication | ||
| Publication | ||
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | FY2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | FY2019 | |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | FY2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | FY2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | FY2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) Â A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | FY2019 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | FY2019 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 1-5, 2016 | Publication | FY2016 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | FY2019 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | FY2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | FY2019 | |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 1703Â1709. | Publication | FY2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | FY2019 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., O'Brien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | FY2019 | |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., O'Brien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | FY2016 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | FY2019 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | FY2016 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | FY2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | FY2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | FY2019 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program - current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | FY2016 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | FY2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | FY2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | FY2019 | |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | FY2016 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | FY2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | FY2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | FY2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | FY2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | FY2019 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | FY2019 | |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | FY2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | FY2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | FY2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | FY2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 17-20, 2016. | Publication | FY2016 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | FY2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | FY2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | FY2019 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 17-21, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | FY2016 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | FY2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | FY2019 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | FY2019 | |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | FY2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | FY2019 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | FY2019 | |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | FY2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | FY2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | FY2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | FY2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | FY2019 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | FY2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | FY2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | FY2019 |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | FY2019 | |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | FY2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | FY2019 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O'Brien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1-5, 2016. | FY2016 | |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | FY2016 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | FY2017 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA's Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea, September 2017 | FY2017 | |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on "In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures". Journal of Nuclear Materials, 484, 168-173. | Publication | FY2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | FY2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 1475-1483). | Publication | FY2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDE-pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | FY2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1-x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | FY2017 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 6429-6434. | Publication | FY2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176-185. | Publication | FY2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 1484-1492. | Publication | FY2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 1373-1382. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™. Journal of Nuclear Materials, 507, 306-315. | Publication | FY2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269-272. | Publication | FY2018 |
| Kilby S.M, Marshall M.A, Choe D.O. et al. (2024). Design of Mini-Plate-1 Irradiation Test for Qualification of High-Density, Low-Enriched U-10Mo Monolithic Fuel. JOM. | Publication | FY2025 |
| Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C. & M. Tippet (2024). Fast Neutron Irradiation Capability in Existing Thermal Test Reactors, Annals of Nuclear Energy, Volume 207, 110731, ISSN 0306-4549. | Publication | FY2025 |
| Wang, Y., Burns, J., Yao, T. & L. Capriotti (2024). Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155209, ISSN 0022-3115. | Publication | FY2025 |
| Wang, Y., Howard, C., Xu, F., Salvato, D., Bawane, K., Murray, D., Frazer, D., Anderson, S., Yao, T., Yeo, S., Kim, J-H, Lee, B-O, Kim, J., Fielding, R. & L. Capriotti (2024). Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155231, ISSN 0022-3115. | Publication | FY2025 |
| Nicodemo G., Zullo G., Cappia F., Van Uffelen P., De Lara A., Luzzi L. & D. Pizzocri (2024). Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity. Journal of Nuclear Materials. 601:155301. | Publication | FY2025 |
| Colldeweih A., P. Petersen, M. Matos, J. Stockwell, R. Hansen, D. Kamerman, D. Lutz & F. Cappia (2025) Post irradiation examinations of FeCrAl cladding in PWR conditions Journal of Nuclear Materials Vol. 603, 155402 | Publication | FY2025 |
| Dabney, T., Sasidhar, K.N., Willing, E., Lukas, C., Quillin, K., Yeon, H. & K. Sridharan (2025). Microstructural Evolution in Ion Irradiated Cold Spray Cr Coated Zr-alloy, Journal of Nuclear Materials, vol. 606, 155652 | Publication | FY2025 |
| Chen, D., Burns, J., Wright, K. E., Salvato, D., Yao, T. & L. Capriotti (2025). Transmission electron microscopy characterization of fuel cladding chemical interaction between minor actinides bearing U-Pu-Zr fuel and AIM1 cladding. Journal of Nuclear Materials, 607, 155667. | Publication | FY2025 |
| Kancharla R.R, Chuirazzi W.C, Kane J.J et al. (2025). X-ray computed tomography of deconsolidated TRISO particles from the AGR-5/6/7 irradiation experiment capsule 1 compact. J Nucl Mater. ; 607:155704. doi:10.1016/j.jnucmat.2025.155704. | Publication | FY2025 |
| Meehan N.A., Gorton J.P., Capps N.A. & N.R. Brown (2025). Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions. Journal of Nuclear Materials, 2025;609:155745. doi:10.1016/j.jnucmat.155745. | Publication | FY2025 |
| Middlemas, S., & C. Adkins (2025). A critical analysis of U-Pu-Zr phase transitions using calorimetric, microstructural, and phase equilibria data. Journal of Nuclear Materials, 612, 155778. | Publication | FY2025 |
| Probert A., Swearingen A., Schulthess J., Capriotti L., Jensen C. & A. Aitkaliyeva (2025). Comparative Post-irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Steady-state Irradiation Behavior Against Historical and Modeled Fuel Performance. Journal of Nuclear Materials.; 610:155782. | Publication | FY2025 |
| Dhulipala, S. L. N., Simon, P.-C. A., Demkowicz, P. A., Hirschhorn, J. A. & S. R. Novascone (2025). Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches. Journal of Nuclear Materials, 610, 155795. | Publication | FY2025 |
| Salvato, D., Nguyen, B.-P., Wang, Y., Di Lemma, F. G., Capriotti, L., Aitkaliyeva, A. & T. Yao, (2025). TEM Characterization of Two Variants of Fuel Cladding Chemical Interaction in a HT-9 Clad U-10Zr Fuel. Variant 1: FCCI with a Zr Rind. Journal of Nuclear Materials, 614, 155855. | Publication | FY2025 |
| Espersen, J. I., Garrison, B. E., Cervenka, P., Seshadri, A., Linton, K., Shirvan, K., Capps N.A & N.R. Brown (2025). The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions. Journal of Nuclear Materials, 155910. | Publication | FY2025 |
| Skerjanc, W. F., Jiang, W., Demkowicz, P. A. & J.D. Stempien (2025). Evaluation of AGR-3/4 In-pile Silver Release Predictions Against Post-irradiation Examination measurements. Journal of Nuclear Materials, 615, 155942. | Publication | FY2025 |
| Mauseth, T., Dunzik-Gougar, M. L. & F. Teng (2025). Micro-tensile Characteristics of As-fabricated and Irradiated AGR-2 TRISO Fuel Particle Buffer, IPyC, and Buffer-IPyC Interlayer Regions. Journal of Nuclear Materials, 156086. | Publication | FY2025 |
| Capriotti, L., Di Lemma, F., Salvato, D., Xu, F., Tang, Y., Paaren, K.M., Swearingen, A.L., Jensen, C.B., Wang, Y. & D.L. Porter (2025). An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in HT9/U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis. Journal of Nuclear Materials, p.156092. | Publication | FY2025 |
| Pradhan A, Xu F, Salvato D, et al. (2024). Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning. Mater Charact. 2024;218(1):114524. | Publication | FY2025 |
| Rittenhouse J., Pradhan A., Kamerman D.W, Burns J., Xu F., Wen H. & T. Yao (2025) Site-specific Nanoscale Characterization of Zirconium Hydrides in the Hydride Rim Structure of Hydrogen-charged Zircaloy-4 Cladding. Mater Charact ;224:115006. | Publication | FY2025 |
| Yang, G., Nguyen, B.-P., Rittenhouse, J. E., Xu, F., Gonderman, S., Gazza, J., Xu, P. & T.Yao (2025). Investigating Grain Structure and Microcracking in SiCf-SiCm Composites Using 4D-STEM. Materials Characterization, 225, 115165. | Publication | FY2025 |
| Zhao, L., Xu, F., Porter, D. L. & Y. Wang (2025). Quantification of line dislocations in FFTF irradiated HT9 cladding by deep learning method. Materials Characterization, 227, 115322. | Publication | FY2025 |
| Beausoleil, G. L., Curnutt, B., Moorehead, M. & Bascom, A. (2025). Multi-principal element alloys for fast reactor cladding applications. Nuclear Engineering and Technology, 57(4), 103303. | Publication | FY2025 |
| Chuirazzi, W., Bush, J., Gross, B., Bryant, M., Clark, K., Cook, M., Burtenshaw, J., Price, J., Morankar, S., Blattner, M., Landon, R., Galloway, K., Stanger, J., Stamos, R., Duke, J., Watt, C. & J. Stempien (2025). Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel. Nuclear Engineering and Technology, 57(10), 103726. | Publication | FY2025 |
| Seo S., Folsom C., Jensen C. et al. (2024). International Fuel Performance Study of Fresh Fuel Experiments for PCMI Effects During RIA Experiments. Nuclear Engineering and Design; 430:113673. | Publication | FY2025 |
| Moussaoui, M. A., Anderson, K. S., Yoo, J., & N.E. Woolstenhulme (2025) Device for steam cladding oxidation testing at TREAT, Nuclear Engineering and Design, 445, 114441. | Publication | FY2025 |
| Downey C.M., Oldham N., Fleming A., Chapman D., Mata Cruz A. & K. Ellis (2024). Design of a First-of-a-kind Instrumented Advanced Test Reactor Irradiation Capsule Experiment for in Situ Thermal Conductivity Measurements of Metallic Fuel. Prog Nucl Energy.;175:105325. | Publication | FY2025 |
| Umretiya, R.V, Qu, H., Yin, L., Jurewicz, T.B., Gupta, V.K., Drobnjak, M., Knussman, M. Hoffman, A.K. & R.B. Rebak (2024). Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments, npj Mater Degrad 8, 88. | Publication | FY2025 |
| Zhao, L., Wang, Y., & F. Xu (2025). Accurate Segmentation of Localized Fuel Cladding Chemical Interaction Layers in SEM Micrographs with Deep Learning Method. Scientific Reports, 15, 28878. | Publication | FY2025 |
| Chavez, R., Anand, N.K. & Hassan, Y. & S. Girimaji (2024) "Flow Over a Sphere at Elevated Pressures: An Analysis of the Near-Wake Using Spectral Proper Orthogonal Decomposition" Physics of Fluids, November 2024, Vol. 36, 115155 (1-17) Issue 11, selected as Editors Pick. | Publication | FY2025 |
| Hawkes, G., Pham, B. & C. Otani (2024). Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps. Nuclear Science and Engineering, 126. | Publication | FY2025 |
| Riet, A. A. & J.D. Stempien (2025). Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation. Nuclear Science and Engineering, 112. | Publication | FY2025 |
| Petersen, P. G., Hansen, R. S., Cappia, F., Kamerman, D., Baird, K. & C. Christensen (2024). Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens. Journal of Testing and Evaluation, 52(6), 33263345. | Publication | FY2025 |
| Capps, N., Yan, Y., Harp, J., Ridley, M. & R. Salko Jr. (2024). Recent High Burnup LOCA Testing at Oak Ridge National Laboratory (ORNL/SPR-2024/3544). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Singh G., Yu J., Xu F., Yao T. & P. Xu (2024). Multiscale Modeling of Silicon Carbide Cladding for Nuclear Applications: Thermal Performance Modeling. Energies. 2024; 17(23):6124. | Publication | FY2025 |
| Cakmak, E., Cinbiz, M. N., Arregui-Mena, J. D., Deck, C. & T. Koyanagi (2025). Damage Progression and Failure of SiC/SiC Composite Tubes under Hard-Contact Radial Expansion. Composites Part B: Engineering, 112869. | Publication | FY2025 |
| Dolley, E. J., Zhang, W., Zorn, G., Sand, T. & R.B. Rebak (2024) "Enhanced mechanical properties and wear resistance of FeCrAl alloys at~ 300 C and Higher temperatures." JOM 76, no. 8 (2024): 4123-4130. | Publication | FY2025 |
| Nagothi, B.S., Qu, H., Zhang, W., Umretiya, R.V., Dolley, E.& R.B. Rebak (2024). "Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding." Materials 17, no. 7: 1633. | Publication | FY2025 |
| Qu, H., Yin, L., Larsen, M., and R.B. Rebak (2024). "Distinctive oxide films develop on the surface of fecral as the environment changes for nuclear fuel cladding." Corrosion and Materials Degradation 5, no. 1: 109-123. | Publication | FY2025 |
| Woolstenhulme, N. et al. (2025). SPARC - Plans for a New Critical Experiment Facility with a Horizontal Split Table (INL/RPT-25-84855). Idaho National Laboratory, Idaho Falls, ID. | Publication | FY2025 |
| Yang, Y., Weicheng Z. & C. Massey (2025). Computational Design of Improved Fast Reactor Cladding (ORNL/TM-2025/3953), Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., Laug, D.V. & J.D. Stempien (2024). Micro-tensile Properties of Fueled Irradiated AGR-2 TRISO-coated Particle Buffer, IPyC, and SiC Interlayer Regions. Presented at the 2024 Nuclear Materials (NuMat) Conference. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L. & J.D. Stempien (2024). Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., & J.D. Stempien (2024). Fracture Behavior Considerations for the TRISO Particle Matrix. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles. Presented at the 2025 Nuclear Science User Facilities (NSUF) Annual Program Review. | Publication | FY2025 |
| Qu, H.J., Chikhalikar, A.S., Abouelella, H., Roy, I., Rajendran, R., Nagothi, B.S., Umretiya, R., Hoffman, A.K. & R.B. Rebak (2024). "Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments." Corrosion Science 229 (2024): 111870. | Publication | FY2025 |
| Roy, R., Chatterjee, A., Mondal, S., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya.(2025). "Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions." Corrosion Science: 112965. | Publication | FY2025 |
| Mondal, S., Chatterjee, A., Roy, R., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya. "Synergistic Roles of Cr and Mo in Low Temperature Steam Oxidation of FeCrAl Alloys." Corrosion Science (2025): 113107. | Publication | FY2025 |
| Rajendran, R., Chikhalikar, A.S., Roy, I., Abouelella, H., Qu, H.J., Umretiya, R.V., Hoffman, A.K., and R.B. Rebak (2024). "Effect of aging and ?segregation on oxidation and electrochemical behavior of FeCrAl alloys." Journal of Nuclear Materials 588: 154751. | Publication | FY2025 |
| Joyce, L., Wang, P., Umretiya, R.V., Hoffman, A. & Y. Xie (2024). "Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water." Journal of Nuclear Materials 593: 154987. | Publication | FY2025 |
| Chikhalikar, A.S., Qu, H., Abouelella, H., Nagothi, B., Rajendran, R., Roy, I., Umretiya, R., Hoffman, A. & R. Rebak, . "Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys." Journal of Nuclear Materials 598 (2024): 155179. | Publication | FY2025 |
| Nelson M., Samuha S., Kombaiah B., Kamerman D. & P. Hosemann (2024). Enhanced Stress Relaxation Behavior Via Basal ?a?dislocation activity in Zircaloy-4 cladding. Journal of Nuclear Materials ;601:155337. | Publication | FY2025 |
| Hirschhorn J.A., Aagesen L.K., Jiang C. & G.L. Beausoleil (2025). Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nucl Eng Des ;432:113811. | Publication | FY2025 |
| Ravi, S.K., Comlek, Y., Pathak, A., Gupta, V., Umretiya, R., Hoffman, A., Pilania, G. et al. (2025) "Interpretable multi-source data fusion through Latent Variable Gaussian Process." Engineering Applications of Artificial Intelligence 145: 110033. | Publication | FY2025 |
| Umretiya, R.V., Chikhalikar, A., Elward, B., Moreira, T.A., Anderson, M., Rebak, R.B. & J.V. Rojas (2024). "The Effect of Ramp Heating on the Microstructure and Surface Chemistry of APMT FeCrAl Alloy." Nuclear Materials and Energy 38: 101567. | Publication | FY2025 |
| Joyce, L., Umretiya, R.V., Qu, H., Shang, Z. & Y. Xie (2025). "Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400900° C." Nuclear Materials and Energy : 101953. | Publication | FY2025 |
| Bermudez, S., Erdogan, F., Davis, V., Rojas, J.V. & R.V. Umretiya (2025). "Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000° C)." Nuclear Materials and Energy : 101972. | Publication | FY2025 |
| Bawane, K.K., Yang, G., Yao, T., Xu, F., Xu, P., Gonderman, S. & J. Gazza (2025). Microstructure Analysis of Silicon Carbide Cladding Using 4D-STEM. Paper presented at M&M 2025. | FY2025 | |
| Cappia F., Colldeweih, A., Frazer, D., Hansen, R., Petersen, P., Stockwell, J., Anderson, S., Charbeneau, J., Kamerman, D. (2024) Effect of Metal Contaminants on Cr Coating Performance after Irradiation in the Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Carvajal, J. (2025). In-Rod Sensor System Irradiation Test Results with Segmented Fuel Assembly, accepted for the 14th International Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2025), Chicago. | FY2025 | |
| Cervenka, P., Seshadri A., Sevecek M., Cvrcek L. & K. Shirvan (2024). Development of PVD Cr-(Nb) coated fuel cladding with enhanced accident tolerance, Presented at the Nuclear Materials Conference. | FY2025 | |
| Chavez, R. (2025). Fluid Dynamics and Thermal Effects of Flow Over a Sphere at High Pressures and Graphitic Dust Behavior in Square Channels, PhD Dissertation, Texas A&M University. | FY2025 | |
| Chavez, R., Anand, N.K. & Y. Hassan (2025) High-Pressure Experimental Analysis of Thermal Effects on Near-Wake Turbulence and Energy Distribution of Flow over a Heated Sphere, Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Colldeweih A., Kamerman, D., Matos, M., Bawane, K., J. Stockwell, J., A. Pradhan, A., Hansen, R., Cappia, F. & D. Lutz (2024) Corrosion of Neutron Irradiated FeCrAl in the ATR Water Loop TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Dabney, T., Sasidhar, K.N., Willing, E., Eftink, B., Li, N., Maier, B., Walters, J. & K. Sridharan (2025). Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding, Symposium on Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Hansen R., Colldeweih, A., Petersen, P., Stockwell, J., Charboneau, J., Albuquerque, L., Baird, K., Kamerman, D. & F. Cappia (2024) Examinations of Cr-Coated M5 Cladding Irradiated at the INL Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Harp, J., Yan, Y., Morris, R., Baldwin, C., Jones, M. & N. Capps (2024). Development of Fission Gas Release Cabilities to Study High Burnup Commercial Fuel Performance under Loss of Coolant Accident Conditions. Proc. TopFuel 2024, Grenoble, France. | FY2025 | |
| Jung, W., Dunbar, C., Jo, J.Y., Sridharan, K. & H. Yeom (2025). Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr cladding under Multiple Quench Tests, Symposium on Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Karlsson, T. Y. (2025). Fuel Qualification: Near-Term Activities & Needs for Molten Salt Fuels. Presented at the EPRI Advanced Reactor Workshop. | FY2025 | |
| Kosmidou, M., Broussard, A., Lian, J. & E. Kardoulaki (2025). Filling of data gaps for the development of ceramic fuels, pp. 23.Materials in Nuclear Energy Systems (MiNES) 2025 Conference. | FY2025 | |
| Li, N., Xie, D., Kim, H., Dabney, T., Eftink, B., Sridharan, K., Graening, T., Nelson, A., Fensin, S.& S. Maloy (2025). In Situ Micro-Cantilever Beam Bending Tests to Assess the Adhesion Strength of Cr Coatings on Zry-4, Symposium on Mechanical Behavior Related to Interface Physics IV, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Microstructural Characterization of AGR-2 TRISO Particle Buffer, IPyC, and Buffer-IPyC Interfaces. Presented at the 2025 Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). | FY2025 | |
| Pham, B. T., Hawkes, G. L., Lybeck, N. J., Otani, C. & P.A. Demkowicz (2025). Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment. Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Seshadri A., Cervenka P., Fazi A., Sevecek M., Carpenter D., Cetiner N., Motta A., Ishak C., Fei Z., Raiman S., Xu P. & K. Shirvan. In-pile hydrothermal corrosion behavior of Zirconium Alloys with and without ATF Coatings, Presented at 21st ASTM International Symposium on Zirconium in the Nuclear Industry. | FY2025 | |
| Shirvan K., Cervenka P., Fazi A. & A. Seshadri (2025). Experimental Investigation of CrNb Coatings for PWRs and BWRs. Paper at the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. | FY2025 | |
| Sridharan, K. Maier, B., Dabney, T., Willing, E., Pocquette, N. Lukas, C., Anderson, N. & H. Yeom (2025). Cold Spray Materials Deposition Technology for Nuclear Energy Systems, Symposium on Advances in Materials Deposition by Cold Spray and Related Technologies, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Walter, J., Roberts, E., Fredrick, K., Viands, D. & X. Huang (2025). The Effect of Chromium Coating Microstructure and Oxide Films on Hydrogen Uptake in Zirconium-alloy Nuclear Fuel Cladding, 21st International Symposium on Zirconium in the Nuclear Industry, Aix-en-Provence, France. | FY2025 | |
| Woolstenhulme, N., Martin, N., DeHart, M., Percher, C., Cutler, T., Wieselquist, W. (2025). SPARC, an Effort to Reestablish a Horizontal Split Table Critical Facility for HALEU Experiments and Beyond. Paper presented at the NCSD 2025 Annual Meeting. | FY2025 | |
| Yuan, G., Cook, D.H., Barnard, H., Lahoda, E., Xu, P., Ritchie, R.O. & D. Liu (2025). Improved Damage Tolerance of SiC-Based Nuclear Fuel Cladding with Novel Multi-Layered SiC Coating Design at 1200°C, Materials & Design, Volume 256, August 2025, 114260. | Publication | FY2025 |
| Zhang, S., Ma, Z., Xu, P. (2024). Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors, 2024 ANS Annual Meeting. | FY2025 | |
| Zhang, J., Xu, P., Sevecek, M., Sim, K.S. & A. Khaperskaia (2025). Contribution of IAEA Coordinated Research Projects to Light Water Reactors Advanced Technology Fuel Testing and Simulation, Nuclear Engineering and Design 418, 112910. | Publication | FY2025 |
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 12001207. Melville, NY, 2012. | Publication | 2013 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | FY2016 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | FY2016 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | 2014 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | FY2016 | |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | 2014 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | 2015 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | FY2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | FY2016 |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | FY2016 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | FY2016 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | 2018 | |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | FY2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | FY2016 | |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | 2015 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OÂBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155163. | Publication | 2013 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | FY2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 1521, 2013. ASME. | Publication | 2015 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | FY2016 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | FY2016 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | FY2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | FY2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | FY2016 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | 2016 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | FY2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | FY2016 | |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | 2016 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | FY2016 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | FY2016 | |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | 2019 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | 2016 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | FY2016 | |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | 2018 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | FY2016 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | 2019 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | FY2016 | |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ?295 °C to ?6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | 2015 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | FY2016 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | 2010 | |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | FY2016 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | 2010 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | 2011 | |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | FY2016 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Mariani, R. D., Porter, D. L., OHolleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | 2012 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | 2019 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | 2018 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | 2019 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | FY2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | FY2016 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | 2019 | |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | FY2016 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | 2017 | |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | FY2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | 2017 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | 2018 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | FY2016 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | FY2016 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | 2012 | |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | FY2016 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | 2018 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | FY2016 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | 2018 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the ULaO system. Journal of Nuclear Materials, 456, 142-150. | Publication | 2015 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1?yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | 2013 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | 2017 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures. Journal of Nuclear Materials, 484, 168-173. | Publication | 2017 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | FY2016 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | 2017 |
| Cole, J. I., T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | FY2010 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Koyanagi, T., Lance, M. J., & Katoh, Y. (2016). Quantification of irradiation defects in beta-silicon carbide using Raman spectroscopy. Scripta Materialia, 125, 58-62. | Publication | FY2016 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | 2010 | |
| Kristiansen, P. (2016, August). Preliminary neutronics calculations for the proposed accident tolerant fuel (ATF) test for DOE. Institutt for energiteknikk OECD, Halden Reactor Project, CP-NOTE, 16-22. | FY2016 | |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., & Sohn, Y. H. (2011). Thermotransport in ?(bcc) UZr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | 2011 |
| Law, M., Carr, D. G., & Vogel, S. C. (2015). Materials for the nuclear energy sector. In Neutron applications in materials for energy. Springer International Publishing. | Publication | FY2016 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | 2013 |
| Liu, M., Ryals, M., Ali, A., Blandford, E. D., Jensen, C., Condie, K., Svoboda, J., & OÂBrien, R. (2016). Development of electrical capacitance sensors for accident tolerant fuel (ATF) testing at the Transient Reactor Test (TREAT) Facility. In Proceedings of Test, Research and Training Reactors (TRTR) 2016 Conference, Albuquerque, NM. | Publication | FY2016 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | 2014 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 64296434. | Publication | 2018 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Energy-resolved neutron imaging for interrogation of nuclear materials. In Proceedings of the Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC), Santa Fe, NM, September 25-30, 2016. | FY2016 | |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | 2011 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., et al. (2016). Neutron characterization of UN/U-Si accident tolerant fuel prior to irradiation. In Proceedings of Top Fuel 2016, Boise, ID, 11-14 September 2016. | FY2016 | |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgONd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | 2013 |
| Losko, A. S., Vogel, S. C., Bourke, M. A., Voit, S. L., McClellan, K. J., Mocko, M., Byler, D. D., Tremsin, A. S., & Hosemann, P. (2016). Characterization of fresh nuclear fuel using time-of-flight neutrons. Transactions of the American Nuclear Society, 114(1), 1083-1086. New Orleans, LA. June 12-16, 2016. | Publication | FY2016 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | 2014 |
| Maier, B. R., Garcia-Diaz, B. L., Hauch, B., Olson, L. C., Sindelar, R. L., & Sridharan, K. (2015). Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding. Journal of Nuclear Materials, 466, 712-717. | Publication | FY2016 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(13), 441-447. | Publication | 2014 |
| Massey, C. P., Terrani, K. A., Dryepondt, S. N., & Pint, B. A. (2016). Cladding burst behavior of Fe-based alloys under LOCA. Journal of Nuclear Materials, 470, 128-138. | Publication | FY2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | 2015 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | FY2011 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | FY2016 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | 2010 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(1-3), 2-7. | Publication | FY2011 |
| OÂBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | FY2016 | |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Nuclear Energy Agency. (2014). Uranium 2014: Resources, production and demand. OECD Publishing. 488 | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | FY2016 |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| OBrien, R. C., Woolstenhulme, N. E., Folsom, C. P., Jensen, C., Wachs, D. M., & Beasley, A. A. (June 22-24). Resumption of transient testing at the Idaho National Laboratory TREAT reactor: Development of experimental and analytical capabilities in support of the Accident Tolerant Fuels campaign. Proceedings of OECD/NEA Workshop on Pellet Cladding Interaction (PCI) in Water Cooled Reactors, Lucca, Italy. | 2016 | |
| Cole, J. I., O'Holleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | FY2011 | |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | FY2016 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | 2019 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Hurley, D. H., Khafizov, M., Shinde, S., Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | FY2011 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | FY2016 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Janney, D. E., Kennedy, J. R. (2010). As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | FY2011 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | 2018 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | FY2016 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(13), 520-533. | Publication | 2014 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | FY2016 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | 2018 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | FY2016 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | 2015 |
| Mohanty, R. R., Bush, J., Okuniewski, M. A., Sohn, Y. H. (2011). Thermotransport in γ(bcc) U-Zr alloys: A phase-field model study. Journal of Nuclear Materials, 414(2), 211-216. | Publication | FY2011 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | FY2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, D., Mouche, P. A., Zhong, W., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). TEM study of Zircaloy 2 with FeCrAl layer under simulated BWR environment. In Transactions of the American Nuclear Society, 114(1), 1059-1060. Poster presented at the 2016 ANS Annual Meeting, New Orleans, LA. | Publication | 2016 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | 2010 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | FY2016 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Park, Y., Huang, K., Paz y Puente, A., & et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 7282. | Publication | 2013 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | FY2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Pereira da Silva, J. G., Al-Qureshi, H. A., Keil, F., & Janssen, R. (2016). A dynamic bifurcation criterion for thermal runaway during the flash sintering of ceramics. Journal of the European Ceramic Society, 36(5), 1261-1267. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | FY2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Petrie, C. M., & Terrani, K. A. (2016). Thermal analysis of a flexible rabbit design for irradiating PWR cladding. FY-16 DOE-NE FCRD Report: ORNL/TM-2016/197. Oak Ridge National Laboratory. | Publication | 2016 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | FY2016 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | 2018 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | FY2016 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | 2018 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | FY2016 | |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | 2019 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | FY2016 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | 2019 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | FY2016 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | FY2016 | |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Petrie, C. M., Koyanagi, T., McDuffee, J. L., Deck, C. P., Katoh, Y., & Terrani, K. A. (2017). Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux. Journal of Nuclear Materials, 491, 94-104. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | FY2016 |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | 2012 | |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | FY2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | 2014 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | FY2016 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | 2015 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | FY2016 | |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | 2015 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | FY2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | 2015 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | FY2016 | |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 1720, 2016. | Publication | 2016 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | FY2016 | |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 1417, 2014. | Publication | 2014 |
| Mariani, R. D., Porter, D. L., O'Holleran, T. P., Hayes, S. L., & Kennedy, J. R. (2011). Lanthanides in metallic nuclear fuels: Their behavior and methods for their control. Journal of Nuclear Materials, 419(1-3), 263-271. | Publication | FY2012 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | FY2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. (2016). ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Proceedings of IAEA Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA-TECDOC-1797. International Atomic Energy Agency. | Publication | 2016 |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | FY2016 | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 1317, 2014 | Publication | 2015 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | FY2016 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | FY2016 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | 2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | FY2016 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors (pp. 1475-1483). | Publication | 2017 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | 2018 | |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | FY2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Rebak, R. B. (2015). Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metallurgical and Materials Transactions E, 2(4), 197-207. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 2089-2107. | Publication | FY2013 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | FY2016 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176185. | Publication | 2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | FY2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Rebak, R. B., & Ellis, D. D. (2016). Passivation characteristics of ferritic stainless materials in simulated reactor environments. Paper 7452, Corrosion 2016. NACE International, Houston, TX. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | FY2016 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | 2019 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(1-3), 1-8. | Publication | FY2013 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | FY2016 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | 2017 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of U-Pu-Zr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | FY2013 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 14841492. | Publication | 2018 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | FY2017 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | FY2017 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | 2019 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | FY2017 | |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | 2019 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | FY2017 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | FY2017 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Rebak, R. B., Kim, Y.-J., Gynnerstedt, J., Terrani, K. A., & Stachowski, R. E. (2016, September). Fabrication of FeCrAl cladding for accident tolerant fuel. Paper presented at Top Fuel 2016, Boise, Idaho. | Publication | 2016 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417-428. | Publication | FY2013 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | 2017 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I-Mechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | FY2013 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 1721, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | 2016 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II- Mechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | FY2013 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | FY2017 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Rebak, R. B., Terrani, K. A., Gassmann, W., Williams, J., Fawcett, R. M., & Stachowski, R. E. (2016). Minimizing risk in nuclear power plant operation by using accident tolerant FeCrAl cladding. Paper RISK16-8330, NACE International Corrosion Risk Management Conference, Houston, TX, May 23-25, 2016. | Publication | 2016 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Dickerson, P., Byler, D., & McClellan, K. (2013). Microstructurally explicit simulation of intergranular mass transport in oxide nuclear fuels. Nuclear Technology, 182(2), 155-163. | Publication | FY2013 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | FY2017 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Reiche, H. M., & Vogel, S. C. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. In Proceedings of Top Fuel 2016, Boise, ID, September 11-14, 2016. | Publication | 2016 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | FY2017 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| Reiche, H. M., Vogel, S. C., & Tang, M. (2016). In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction. Journal of Nuclear Materials, 471, 308-316. | Publication | 2016 |
| McMurray, J. W., Shin, D., Slone, B. W., & Besmann, T. M. (2013). Thermochemical modeling of the U1-yGdyO2±x phase. Journal of Nuclear Materials, 443(1-3), 588-595. | Publication | FY2013 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | FY2017 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | 2011 |
| Nelson, A. T., Giachino, M. M., Nino, J. C., & McClellan, K. J. (2014). Effect of composition on thermal conductivity of MgO-Nd2Zr2O7 composites for inert matrix materials. Journal of Nuclear Materials, 444(1-3), 385-392. | Publication | FY2013 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | FY2017 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | 2019 |
| Park, Y., Huang, K., Paz y Puente, A., et al. (2015). Diffusional interaction between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C). Metallurgical and Materials Transactions A, 46(1), 72-82. | Publication | FY2013 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | FY2017 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | 2015 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145-154. | Publication | FY2013 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | FY2017 |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Robb, K. R. (2015). FeCrAl accident tolerant fuel response during BWR severe accidents. In Proceedings of the 21st International Quench Workshop (QUENCH) (ISBN 978-3-923704-90-3), Karlsruhe, Germany, October 27-29, 2015. | 2016 | |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | FY2013 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | FY2017 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Robb, K. R., & Powers, J. J. (2014, October 2730). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | 2015 | |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750°C in FFTF. Journal of Nuclear Materials, 428(1-3), 170-175. | Publication | FY2013 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | FY2017 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Robb, K. R., McMurray, J. W., & Terrani, K. A. (2016). M2FT-16OR020205042: Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL/TM-2016/237. Oak Ridge National Laboratory, June 2016. | Publication | 2016 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems  Water Reactors. | Publication | FY2017 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | FY2017 | |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDEA pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | 2017 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9-y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | FY2013 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | FY2017 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Rudman, K., Dickerson, P., Byler, D., McDonald, R., Lim, H., Peralta, P., & McClellan, K. (2013). Three-dimensional characterization of sintered UO2+x: Effects of oxygen content on microstructure and its evolution. Nuclear Technology, 182(2), 145154. | Publication | 2013 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | FY2017 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | 2010 | |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(1-3), 206-213. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | FY2017 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Saleh, T. A., Quintana, M. E., & Romero, T. J. (2016). Tensile tests from the StipV irradiation. Submitted for milestone: Complete and report on tensile testing of STIP V FeCrAl specimens (M3FT-16LA020202085). LA-UR-16-22503. March 30, 2016. | 2016 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | FY2017 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | 2017 | |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | FY2017 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Schappel, D., Terrani, K., Powers, J., Snead, L. L., & Wirth, B. D. (2016). Thermo mechanical analysis of fully ceramic microencapsulated fuel during in-pile operation. In Transactions of the 2016 LWR Fuel Performance Meeting (Top Fuel, 2016), Boise, ID, USA. | Publication | 2016 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | FY2017 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | 2019 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | 2017 | |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | FY2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | FY2017 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | 2019 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 - The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | FY2014 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | FY2017 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | 2018 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(1-3), 263-272. | Publication | FY2014 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | FY2017 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | 2019 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(1-3), 290-299. | Publication | FY2014 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | 2019 | |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(1-3), 39-48. | Publication | FY2014 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | FY2017 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | 2019 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | 2018 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | 2018 |
| Koyanagi, T., Katoh, Y., Singh, G., & Snead, M. (2017). SiC/SiC cladding materials properties handbook (ORNL/SPR-2017/385). Oak Ridge National Laboratory. | Publication | FY2017 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| eve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold spraycoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | 2018 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction. Journal of Nuclear Materials, 448(1-3), 534-540. | Publication | FY2014 |
| Li, X., Samin, A., Zhang, J., Unal, C., & Mariani, R. D. (2017). Ab-initio molecular dynamics study of lanthanides in liquid sodium. Journal of Nuclear Materials, 484, 98-102. | Publication | FY2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | 2017 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238-251. | Publication | FY2014 |
| Matthews, C., Galloway, J., & Unal, C. (2017, June 11-15). Advanced simulation aided metallic fuel design. Paper presented at the ANS 2017 Summer Meeting, San Francisco. (LA-UR-17-2044). | FY2017 | |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Shamma, M., Caspi, E. N., Anasori, B., Clausen, B., Brown, D. W., Vogel, S. C., Presser, V., Amini, S., Yeheskel, O., & Barsoum, M. W. (2015). In situ neutron diffraction evidence for fully reversible dislocation motion in highly textured polycrystalline Ti2AlC samples. Acta Materialia, 98, 51-63. | Publication | 2016 |
| Matthews, C., Galloway, J., Unal, C., Novascone, S., & Williamson, R. (2017, June 26-29). BISON for metallic fuels modeling. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-366). | Publication | FY2017 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | 2018 |
| Matthews, C., Unal, C., Galloway, J., Keiser, D. D., & Hayes, S. L. (2017). Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review. Nuclear Technology, 198(3), 231-259. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh, & J. Matyá (Eds.), Ceramic Materials for Energy Applications IV. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(1-3), 162-167. | Publication | FY2014 |
| Medvedev, P., Hayes, S., Bays, S., Novascone, S., & Capriotti, L. (2018). Testing fast reactor fuels in a thermal reactor. Nuclear Engineering and Design, 328, 154-160. | Publication | FY2017 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | 2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(1-3), 497-511. | Publication | FY2014 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Shin, D., & Besmann, T. M. (2013). Thermodynamic modeling of the (U,La)O2±x solid solution phase. Journal of Nuclear Materials, 433(1-3), 227-232. | Publication | 2013 |
| Middleburgh, S., Lahoda, E., Luszck, K., Grimes, R., Andersson, D., Stanek, C., & Besmann, T. (2017, January). Ongoing work on modelling of UN-U3Si2 fuel. Paper presented at the ICACC, Daytona Beach, FL. | FY2017 | |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | 2018 |
| Oelrich, R., Ray, S., Karoutas, Z., Lahoda, E., Boylan, F., Xu, P., Romero, J., & Shah, H. (2017, September 10-14). Overview of Westinghouse Lead Accident Tolerant Fuel Program. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | 2015 |
| Rebak, R. B., Gassmann, W. P., & Terrani, K. A. (2017, February 12-16). Managing nuclear power plant safety with FeCrAl alloy fuel cladding. Paper A0042 presented at IAEA Top Safe 2017, Vienna, Austria. | Publication | FY2017 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | 2015 |
| Rebak, R. B., Larsen, M., & Kim, Y.-J. (2017). Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments. Corrosion Reviews, 35(3), 177-188. | Publication | FY2017 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | 2015 |
| Nelson, A. T., Sooby, E. S., Kim, Y.-J., Cheng, B., & Maloy, S. A. (2014). High temperature oxidation of molybdenum in water vapor environments. Journal of Nuclear Materials, 448(1-3), 441-447. | Publication | FY2014 |
| Rebak, R. B., Terrani, K. A., Gassmann, W. P., & others. (2017). Improving nuclear power plant safety with FeCrAl alloy fuel cladding. MRS Advances, 2, 1217-1224. | Publication | FY2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | 2017 |
| Ott, L. J., Robb, K. R., & Wang, D. (2014). Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. Journal of Nuclear Materials, 448(1-3), 520-533. | Publication | FY2014 |
| Romero, J., Byers, W. A., Wang, G., Mueller, A., & Karoutas, Z. (2017, September 10-14). Simulated severe accident testing for evaluation of accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Singh, G., Sweet, R., Wirth, B. D., Terrani, K. A., & Katoh, Y. (2016). Bison modeling of SiC/SiC cladding including fuel-pellet interaction. ORNL/TM-216/449. Oak Ridge National Laboratory | 2016 | |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | 2015 |
| Powers, J. J., George, N. M., Worrall, A., & Terrani, K. A. (2014). Reactor physics assessment of alternate cladding materials. In Proceedings of 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting (WRFPM 2014). Sendai, Miyagi, Japan, September 14-17, 2014. | Publication | FY2014 |
| Saleh, T. A., Romero, T. J., Quintana, M. E., & Field, K. J. (2017). Mechanical properties of HFIR irradiated FeCrAl alloys. NTR&D milestone report NTRDFUEL-2017-000006, LA-UR-17-28992. | FY2017 | |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 6701498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | 2015 |
| Shih, C., Katoh, Y., Kiggans, J. O., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2014). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. In A. Gyekenyesi, M. Halbig, H.-T. Lin, Y. Katoh,; J. Mat (Eds.), Ceramic Materials for Energy Applications IV. | Publication | FY2014 |
| Schneider, R., LaBarge, N. R., Van De Berg, H., Van Haltern, M., Lahoda, E., & Karoutas, Z. (2017, September 24-28). Estimating the benefits of accident tolerant fuel (ATF). Paper presented at PSA 2017, Pittsburgh, PA. | FY2017 | |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | 2017 |
| Schuster, M., Crawford, C. J., & Rebak, R. B. (2017, March 26-30). Thermal shock resistance of FeCrAl alloys for accident tolerant fuel cladding application. In Proceedings of the CORROSION 2017. NACE-2017-8900 (pp. 1-15). AMPP. New Orleans, Louisiana, USA. | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | 2017 |
| Shah, H., Romero, J., Xu, P., Maier, B., Johnson, G., Walters, J., Dabney, T., Yeom, H., & Sridharan, K. (2017, September 10-14). Development of surface coatings for enhanced accident tolerant fuel. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | Publication | FY2017 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Squires, L. N., & Lessing, P. (2016). Direct chemical reduction of neptunium oxide to neptunium metal using calcium and calcium chloride. Journal of Nuclear Materials, 471, 65-68. | Publication | 2016 |
| Singh, G., Gonczy, S., Lara-Curzio, E., & Katoh, Y. (2017). Interlaboratory round robin axial tensile testing of tubular SiC/SiC specimens (ORNL/SR-2017/397). Oak Ridge National Laboratory. | Publication | FY2017 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | 2018 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | 2018 | |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(1-3), 323-333. | Publication | FY2014 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). The effect of aluminum additions on the oxidation resistance of U3Si2. Journal of Nuclear Materials, 489, 84-90. | Publication | FY2017 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stachowski, R. E., Rebak, R. B., Gassmann, W. P., & Williams, J. (2016). Progress of GE development of accident tolerant fuel FeCrAl cladding. In Top Fuel 2016, Boise, Idaho, September 2016. | Publication | 2016 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | FY2017 |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stauff, N. E., Fei, T., & Kim, T. K. (2016). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FCRD-FUEL-2016-000223). September 30, 2016. | 2016 | |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | FY2017 |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| Stauff, N. E., Fei, T., Kim, T. K., & Hayes, S. L. (2016). Am-bearing blanket transmutation strategies in sodium-cooled fast reactors. In Actinide and Fission Product Partitioning and Transmutation 14th Information Exchange Meeting (14IEMPT), San Diego, October 17-20, 2016. | 2016 | |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(1-3), 304-310. | Publication | FY2014 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | FY2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Stauff, N., Kim, T. K., & Hayes, S. (2017, June). Tradeoff study of advanced transmutation fuels in sodium-cooled fast reactors. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: FR-17, Yekaterinburg, Russian Federation. (CN245-152 PI-81 poster). | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2-MgAl2O4-CeMgAl11O19) and four-phase (3Y-TZP-Al2O3-MgAl2O4-LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | FY2015 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | FY2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Stevens, G. N., Unal, C., Galloway, J., & Matthews, C. (2017, May 3-5). Progressively informed calibration of BISON nuclear fuel models. Paper presented at the 2017 ASME V&V Workshop, Las Vegas, NV. (LA-UR-17-23571). | Publication | 2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | FY2017 | |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Stone, J. G., Schleicher, R., Deck, C. P., Jacobsen, G. M., Khalifa, H. E., & Back, C. A. (2015). Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 466, 682-697. | Publication | 2016 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | FY2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Sun, Z., & Yamamoto, Y. (2017). Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication. Materials Science and Engineering: A, 700, 554-561. | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | FY2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Sun, Z., Bei, H., & Yamamoto, Y. (2017). Microstructural control of FeCrAl alloys using Mo and Nb additions. Materials Characterization, 132, 126-131. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | FY2017 |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Sun, Z., Chen, X., & Yamamoto, Y. (2017). Examination of powder metallurgy vs. induction melting for FeCrAl alloy production (ORNL/TM-2017/381). Oak Ridge National Laboratory. | 2017 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., O'Brien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | FY2015 | |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | FY2017 |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Sweet, R. T., George, N. M., Terrani, K. A., & Wirth, B. D. (2016). Fuel performance analysis of FeCrAl cladding during LWR operation. In Top Fuel 2016 transactions, Boise, ID, 1485-1492. | 2016 | |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-Y-O system. Journal of Nuclear Materials, 460, 5-12. | Publication | FY2015 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | FY2017 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | 2019 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | FY2017 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | 2012 | |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UN-U3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | FY2015 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | FY2017 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | 2014 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | FY2017 | |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | 2014 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system - FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | FY2015 | |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | FY2017 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | 2014 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | FY2017 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | 2014 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | FY2015 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | FY2018 |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Terrani, K. A., et al. (2016). Characterization report on FeCrAl cladding for Halden irradiation, ORNL/TM2016/343, Oak Ridge National Laboratory, July 2016. | 2016 | |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523-537. | Publication | FY2015 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | FY2018 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | FY2018 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| Terrani, K. A., Pint, B. A., Kim, Y.-J., Unocic, K. A., Yang, Y., Silva, C. M., Meyer, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. Journal of Nuclear Materials, 479, 36-47. | Publication | 2016 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015. | Publication | FY2015 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | FY2018 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | 2015 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Toloczko, M. B., Garner, F. A., & Maloy, S. A. (2012). Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40110 dpa at 400750°C in FFTF. Journal of Nuclear Materials, 428(13), 170-175. | Publication | 2013 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | FY2018 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Toloczko, M. B., Garner, F. A., Voyevodin, V. N., Bryk, V. V., Borodin, O. V., Melnychenko, V. V., & Kalchenko, A. S. (2014). Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa. Journal of Nuclear Materials, 453(13), 323-333. | Publication | 2014 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | FY2018 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | 2019 | |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | FY2018 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Unal, C., Matthews, C., Xiang, L., Isler, J., Zhang, J., & Galloway, J. (2017, June 11-15). A potential mechanism for lanthanide transport in metallic fuels. Transactions of the American Nuclear Society, 116, 501-503. San, Francisco, (LA-UR-17-20083). | Publication | 2017 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | FY2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | FY2018 | |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Unal, C., Xiang, L., Isler, J., Matthews, C., Abid, S., Zhang, J., Galloway, J., & Mariani, R. (2017, June 26-29). Modeling of lanthanide transport in metallic fuels: Recent progresses. Paper presented at the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russian Federation. (IAEA-CN-245-350, LA-UR-17-20106). | Publication | 2017 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | FY2018 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | 2014 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | FY2018 | |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | 2013 |
| Lim, H. C., Rudman, K., Krishnan, K., McDonald, R., Peralta, P., Dickerson, P., Byler, D., Stanek, C., & McClellan, K. J. (2013). Microstructural effects on thermal conductivity of uranium oxide: A 3D multi-physics simulation. In Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition, Volume 6B: Energy (Paper No. V06BT07A056). San Diego, California, USA, November 15-21, 2013. ASME. | Publication | FY2015 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | FY2018 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | 2012 |
| Maloy, S. A., Saleh, T. A., Anderoglu, O., Romero, T. J., Odette, G. R., Yamamoto, T., Li, S., Cole, J. I., & Fielding, R. (2016). Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ~295 °C to ~6.5 dpa. Journal of Nuclear Materials, 468, 232-239. | Publication | FY2015 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | FY2018 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| Vogel, S. C., Bourke, M. A., Stanek, C. R., et al. (2016). Summary report of joint FCRD/NEAMS technical experts working meeting on neutron-based NDE. Report for FCRD program, June 3, 2016. | 2016 | |
| McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the U-La-O system. Journal of Nuclear Materials, 456, 142-150. | Publication | FY2015 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Nondestructive examination of UN/U-Si fuel pellets using neutrons (preliminary assessment). Report for FCRD program, March 20, 2016 (LA-UR-16-22179). | Publication | 2016 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | FY2018 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Vogel, S. C., Losko, A. S., Bourke, M. A., McClellan, K. J., et al. (2016). Non-destructive pre-irradiation assessment of UN/U-Si "LANL1" ATF formulation. Report for FCRD program (LA-UR-16-27110) September 15, 2016. | Publication | 2016 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | 2019 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | 2019 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | FY2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | FY2018 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | |
| Powers, J. J., Worrall, A., Robb, K. R., George, N. M., & Maldonado, G. I. ORNL analysis of operational and safety performance for candidate accident tolerant fuel and cladding concepts. In Accident tolerant fuel concepts for light water reactors: Proceedings of a technical meeting (pp. 253-273). IAEA-TECDOC-1797. International Atomic Energy Agency October 13-17, 2014 | Publication | FY2015 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | FY2018 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Wang, J., Mccabe, M., Wu, L., Dong, X., Wang, X., Haskin, T. C., & Corradini, M. L. (2017). Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY short term station black out. Nuclear Engineering and Design, 313, 458-469. | Publication | 2017 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Bailey, N., Garner, F. A., Gigax, J., & Shao, L. (2016). Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 387, 20-28. | Publication | 2017 |
| Robb, K. R., & Powers, J. J. (2014, October 27-30). Predicted system response to station blackout severe accident in a boiling water reactor employing FeCrAl cladding [Poster presentation]. NuMat 14: The Nuclear Materials Conference, Clearwater, Florida. | FY2015 | |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | FY2018 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Wang, J., Toloczko, M. B., Kruska, K., & others. (2017). Carbon contamination during ion irradiation - Accurate detection and characterization of its effect on microstructure of ferritic/martensitic steels. Scientific Reports, 7, 15813. | Publication | 2017 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | FY2018 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Wang, Y., Hurley, D. H., Luther, E. P., Beaux, M. F., Vodnik, D. R., Peterson, R. J., Bennett, B. L., Usov, I. O., Yuan, P., Wang, X., & Khafizov, M. (2018). Characterization of ultralow thermal conductivity in anisotropic pyrolytic carbon coating for thermal management applications. Carbon, 129, 476-485. | Publication | 2017 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | FY2018 | |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | 2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | FY2018 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | 2013 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | FY2018 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| White, J. T., & Nelson, A. T. (2013). Thermal conductivity of UO2+x and U4O9?y. Journal of Nuclear Materials, 443(1-3), 342-350. | Publication | 2013 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | 2015 |
| Koyanagi, T., Katoh, Y., Singh, G., Petrie, C., Deck, C., & Terrani, K. (2018, January 23). Post-irradiation examination of SiC tubes neutron irradiated under a radial high heat flux. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | FY2018 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| White, J. T., Nelson, A. T., Byler, D. D., Valdez, J. A., & McClellan, K. J. (2014). Thermophysical properties of U3Si to 1150K. Journal of Nuclear Materials, 452(13), 304-310. | Publication | 2014 |
| Lahoda, E. (2017, November 1). Approaches for accelerating licensing of ATF products. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | 2015 |
| Sooby Wood, E., Parker, S. S., Nelson, A. T., & Maloy, S. A. (2016). MoSi2 oxidation in 670-1498 K water vapor. Journal of the American Ceramic Society, 99(4), 1412-1419. | Publication | FY2015 |
| Lahoda, E. (2017, October 10). Westinghouse accident tolerant fuel materials. Presentation at the Materials Science and Technology Meeting, Pittsburgh, PA. | FY2018 | |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | 2015 |
| Lin, Y.-P., Fawcett, R. M., Desilva, S., Luz, D. R., Yilmaz, M. O., Davis, P., Rand, R., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | 2019 |
| Long, Y., Kersting, P. J., Linsuain, O., Crede, T. M., & Oelrich, R. L. (2018, September 30-October 4). Fuel performance analysis of EnCore® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | 2019 |
| Maier, B. R., Yeom, H., Johnson, G. O., Dabney, T., Walters, J., Romero, J., Shah, H., Xu, P., & Sridharan, K. (2018). Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors. Journal of Minerals, Metals, and Materials Society (JOM), 70(2), 198-202. | Publication | FY2018 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | 2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Terrani, K. A., & Zinkle, S. J. (2018). Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of low-Cr ODS FeCrAl alloys. Journal of Nuclear Materials, 512, 227-238. | Publication | FY2018 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Matthews, C., Stevens, G., & Unal, C. (2018, June 17-21). Calibration of Zr redistribution models for metallic fuel in BISON. In Transactions of the American Nuclear Society Annual Meeting, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b', INL/EXT-14-33641, Rev 0, November 2014. | 2015 | |
| McMurray, J. W., & Besmann, T. M. (2018). Thermodynamic modeling of nuclear fuel materials. In W. Andreoni & S. Yip (Eds.), Handbook of materials modeling. Springer | Publication | FY2018 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O'Brien, R. C., Snow, S. D., & Wachs, D. M. (2016). Capabilities development for transient testing of advanced nuclear fuels at TREAT. In Proceedings of Top Fuel 2016 Conference, American Nuclear Society - ANS, Boise, ID (pp. 67-76). | Publication | 2016 |
| Woolstenhulme, N. E. and D. M. Wachs, TREAT Water Loop Summary for IRP-NE-1, Task 2b, INL/EXT-14-33641, Rev 0, November 2014. | FY2015 | |
| McMurray, J. W., Kiggans, J. O., Helmreich, G. W., & Terrani, K. A. (2018). Production of near-full density uranium nitride microspheres with a hot isostatic press. Journal of the American Ceramic Society, 101(10), 4492-4497. | Publication | FY2018 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., OBrien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1 5, 2016. | 2016 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | 2015 | |
| Oelrich, R., Ray, S., Karoutas, Z., Xu, P., Romero, J., Shah, H., Lahoda, E., & Boylan, F. (2018, September 30-October 4). Overview of Westinghouse lead accident tolerant fuel program. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., O'Brien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | FY2015 |
| Oelrich, R., Xu, P., Lahoda, E., & Deck, C. (2018, June 18-21). Update on Westinghouse EnCore® accident tolerant fuel program. In Proceedings of the American Nuclear Society (ANS) Meeting, 118(1), 1311-1313, Philadelphia, PA. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Woolstenhulme, N., Baker, C. C., Bess, J. D., Davis, C., Housley, G. K., Jensen, C., OBrien, R. C., & Snow, S. D. (2015, June 7-11). TREAT experiment vehicle design and future plans. Transactions of the American Nuclear Society, 112(1), 369-371. | Publication | 2015 |
| Pal, S., Alam, M. E., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2018). Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy. Acta Materialia, 152, 338-357. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | 2019 | |
| Petrie, C. M., Burns, J. R., Morris, R. N., & Terrani, K. A. (2018). Accelerated irradiation testing of miniature fuel specimens. Transactions of the American Nuclear Society, 118, 1476-1479. | Publication | FY2018 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | 2019 |
| Petrie, C. M., Burns, J. R., Morris, R. N., Smith, K. R., Le Coq, A. G., & Terrani, K. A. (2018). Irradiation of miniature fuel specimens in the High Flux Isotope Reactor (Report No. ORNL/SR-2018/844). Oak Ridge National Laboratory. | FY2018 | |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | 2019 |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | FY2016 | |
| Petrie, C. M., Koyanagi, T., Howard, R. H., Field, K. G., Burns, J. R., & Terrani, K. A. (2018, September 30-October 4). Accelerated irradiation testing of miniature nuclear fuel and cladding specimens. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | 2019 |
| Raftery, A. M., Morris, R. N., Smith, K. R., Helmreich, G. W., Petrie, C. M., Terrani, K. A., & Nelson, A. T. (2018). Development of a characterization methodology for post-irradiation examination of miniature fuel specimens (Report No. ORNL/SPR-2018/918). Oak Ridge National Laboratory. | Publication | FY2018 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Woolum, C., Archibald, K., Moore, G., & Galbraith, S. (2016). Fabrication and qualification of small scale irradiation experiments in support of the Accident Tolerant Fuels Program. In TMS 2016: 145th Annual Meeting & Exhibition: Supplemental Proceedings. TMS (Ed.). | Publication | 2016 |
| Ray, S. (2017, October 31). The need for hot cells for nuclear R&D - The role of hot cells in new fuel development. Presentation at the American Nuclear Society, Washington, D.C. | FY2018 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | 2019 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Wysocki, A., Brown, N. R., Terrani, K. A., & Wachs, D. M. (2016). Potential impact of cladding wettability on LWR transient progression. Transactions of the American Nuclear Society, 115, 473-477. Paper presented at the 2016 Transactions of the American Nuclear Society, ANS 2016, Las Vegas, United States, November 6-10, 2016. | Publication | 2016 |
| Scott, S. M., Yao, T., Lu, F., Xin, G., Zhu, W., & Lian, J. (2017). Fabrication of lanthanum-doped thorium dioxide by high-energy ball milling and spark plasma sintering. Journal of Nuclear Materials, 485, 207-215. | Publication | FY2018 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | 2019 |
| Seshadri, A., & Shirvan, K. (2018). Quenching heat transfer analysis of accident tolerant coated fuel cladding. Nuclear Engineering and Design, 338, 5-15. | Publication | FY2018 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | 2011 |
| Seshadri, A., Phillips, B., & Shirvan, K. (2018). Towards understanding the effects of irradiation on quenching heat transfer. International Journal of Heat and Mass Transfer, 127(Part B), 1087-1095. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | 2011 |
| Âeve?ek, M., Gurgen, A., Seshadri, A., Che, Y., Wagih, M., Phillips, B., Champagne, V., & Shirvan, K. (2018). Development of Cr cold sprayÂcoated fuel cladding with enhanced accident tolerance. Nuclear Engineering and Technology, 50(2), 229-236. | Publication | FY2018 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | 2011 |
| Sheeder, J., Gonderman, S., Jacobsen, G., Khalifa, H. E., Shih, C., Song, E., Shapovalov, K., & Deck, C. P. (2018). Non-destructive evaluation of sealed SiC-SiC composite cladding structures using X-ray computed tomography, pycnometry, and helium leak testing. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL, Jan 21-26, 2018. | Publication | FY2018 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | 2013 |
| Shrestha, K., Yao, T., Lian, J., Antonio, D., Sessim, M., Tonks, M. R., & Gofryk, K. (2019). The grain-size effect on thermal conductivity of uranium dioxide. Journal of Applied Physics, 126(12), 125116. | Publication | FY2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Squires, L. N., King, J. A., Fielding, R. S., & Lessing, P. (2018). Isolation of high purity americium metal via distillation. Journal of Nuclear Materials, 500, 26-32. | Publication | FY2018 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Xu, P., Lahoda, E., & Long, Y. (2017, January). Westinghouse accident tolerant fuel program update on SiC composite cladding development. Paper presented at ICACC, Daytona Beach, FL. | Publication | 2017 |
| Sridharan, K. (2018, March). Invited talk given by UW at the Metallurgical Society (TMS) annual meeting. | FY2018 | |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | 2018 |
| Unal, C., Stevens, G. N., & Matthews, C. (2018, September 30-October 4). Progressive Bayesian calibration of the BISON fuel performance capability. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Xu, P., Lahoda, E., Jacko, R., Boylan, F., & Oelrich, R. (2017, September 10-14). Status of Westinghouse SiC composite cladding fuel development. Paper A0184 presented at the 2017 LWR Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Wagih, M., Spencer, B., Hales, J., & Shirvan, K. (2018). Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings. Annals of Nuclear Energy, 120, 304-318. | Publication | FY2018 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Yamamoto, Y., & Sun, Z. (2017). Quality optimization of commercial FeCrAl tube production (ORNL/TM-2017/338). Oak Ridge National Laboratory. | Publication | 2017 |
| Xu, P., Lahoda, E. J., Lyons, J., Deck, C. P., & Kohse, G. E. (2018, September 30-October 4). Status update on Westinghouse SiC composite cladding fuel development. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | FY2018 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. Journal of Nuclear Materials, 467(Part 2), 703-716. | Publication | 2016 |
| Xu, P., Lahoda, E., Boylan, F., & Oelrich, R. L. (2018, January 21-26). Status update on Westinghouse EnCore SiC/SiC composite cladding development. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, FL. | Publication | FY2018 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yang, X.-d., Gao, J.-c., Wang, Y., & Chang, X. (2008). Low-temperature sintering process for UO2 pellets in partially-oxidative atmosphere. Transactions of Nonferrous Metals Society of China, 18(1), 171-177. | Publication | 2016 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | FY2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yao, T., Scott, S. M., Xin, G., & Lian, J. (2016). TiO2 doped UO2 fuels sintered by spark plasma sintering. Journal of Nuclear Materials, 469, 251-261. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxideÂsilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | FY2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeo, S., McKenna, E., Baney, R., Subhash, G., & Tulenko, J. (2013). Enhanced thermal conductivity of uranium dioxidesilicon carbide composite fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 433(1-3), 66-73. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 13731382. | Publication | 2018 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | 2019 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Yeom, H., Hauch, B., Cao, G., Garcia-Diaz, B., Martinez-Rodriguez, M., Colon-Mercado, H., Olson, L., & Sridharan, K. (2016). Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate. Thin Solid Films, 615, 202-209. | Publication | 2016 |
| Wang, J., Jo, H. J., & Corradini, M. L. (2018). Potential recovery actions from a severe accident in a PWR: MELCOR analysis of a station blackout scenario. Nuclear Technology, 204(1), 1-14. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO. Journal of Nuclear Materials, 507, 306-315. | Publication | 2018 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | FY2016 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | FY2019 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269272. | Publication | 2018 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | FY2019 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Zapata-Solvas, E., Christopoulos, S.-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A., & Lee, W. E. (2017). Experimental synthesis and density functional theory investigation of radiation tolerance of Zr3(Al1-xSix)C2 MAX phases. Journal of the American Ceramic Society, 100, 1377-1387. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | FY2019 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1?x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | 2019 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | FY2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | FY2019 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of ironchromiumaluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | 2016 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | FY2019 |
| Publication | ||
| Publication | ||
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | FY2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | FY2019 | |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | FY2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | FY2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | FY2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) Â A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | FY2019 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | FY2019 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 1-5, 2016 | Publication | FY2016 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | FY2019 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | FY2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | FY2019 | |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 1703Â1709. | Publication | FY2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | FY2019 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., O'Brien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | FY2016 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | FY2019 | |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., O'Brien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | FY2016 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | FY2019 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | FY2016 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | FY2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | FY2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | FY2019 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program - current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | FY2016 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | FY2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | FY2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | FY2019 | |
| Lin, Y. P., Fawcett, R. M., DeSilva, S. S., Lutz, D. R., Yilmaz, M. O., Davis, P., Rand, R. A., Cantonwine, P. E., Rebak, R. B., Dunavant, R., & Satterlee, N. (2018, September 30-October 4). Path towards industrialization of enhanced accident tolerant fuel. Paper A0141 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Lu, R. Y., Walters, J. L., & Qu, J. (2019, September). Assessment of wear coefficients of accident tolerance fuel claddings with coated materials. Paper submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Liu, Y., Bhamji, I., Withers, P. J., Wolfe, D. E., Motta, A. T., & Preuss, M. (2015). Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. Journal of Nuclear Materials, 466, 718-727. | Publication | FY2016 |
| Lyons, J. L., Partezana, J., Byers, W. A., Wang, G., Parsi, A., Walters, J., Romero, J., Mueller, A. J., Shah, H., & Oelrich, R. Jr. (2019, September 22-27). Westinghouse chromium-coated zirconium alloy cladding development and testing. In Proceedings of Top Fuel 2019 (pp. 8-14), Seattle, WA. | Publication | FY2019 |
| Maier, B. R., Yeom, H., Johnson, G., Dabney, T., Hu, J., Baldo, P., Li, M., & Sridharan, K. (2018). In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications. Journal of Nuclear Materials, 512, 320-323. | Publication | FY2019 |
| Maier, B., Yeom, H., Johnson, G., Dabney, T., Walters, J., Xu, P., Romero, J., Shah, H., & Sridharan, K. (2019). Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding. Journal of Nuclear Materials, 519, 247-254. | Publication | FY2019 |
| Massey, C. P., Dryepondt, S. N., Edmondson, P. D., Frith, M. G., Littrell, K. C., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder. Acta Materialia, 166, 1-17. | Publication | FY2019 |
| Massey, C. P., Hoelzer, D. T., Seibert, R. L., Edmondson, P. D., Kini, A., Gault, B., Terrani, K. A., & Zinkle, S. J. (2019). Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration. Journal of Nuclear Materials, 522, 111-122. | Publication | FY2019 |
| Matthews, C., Bieberdorf, N., Capolungo, L., & Andersson, D. (2019). Combined visco-plasticity and swelling in metallic nuclear fuel (Report No. LA-UR-19-25483). Los Alamos National Laboratory. | FY2019 | |
| Oelrich, R., Karoutas, Z., Xu, P., Romero, J., Shah, H., Walters, J., Lahoda, E., Sivack, M., Lyons, J., Czerniak, L., Boylan, F., ?vali, R., Bowman, A., Limbäck, M., Claisse, A., & Wright, J. (2019, September 22-27). Overview of Westinghouse lead EnCore accident tolerant fuel program. In Proceedings of Top Fuel 2019 (pp. 192-196), Seattle, WA. | Publication | FY2019 |
| Petrie, C. M., Burns, J. R., Raftery, A. M., Nelson, A. T., & Terrani, K. A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2019 |
| Petrie, C. M., Burns, J., Morris, R., & Terrani, K. A. (2017). Miniature fuel irradiations in the High Flux Isotope Reactor. In Proceedings of the 40th Enlarged Halden Programme Group Meeting, Lillehammer, Norway. | Publication | FY2019 |
| Prakash, N., Matthews, C., Versino, D., & Unal, C. (2019). A general constitutive framework for the combined creep, plasticity, and swelling behavior of nuclear fuels in an implicit hypoelastic formulation (Report No. LA-UR-20166). Los Alamos National Laboratory. | Publication | FY2019 |
| Rebak, R. B., Blair, R. J., & Gupta, V. K. (2019). Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools. Paper No. C2019-12944, 1-14. NACE International. Nashville, TN. | Publication | FY2019 |
| Rebak, R. B., Gupta, V. K., Drobnjak, M., Keck, D. J., & Dolley, E. J. (2018, September 30-October 4). Overcoming sensitization in welds using FeCrAl alloys. Paper A0052 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Powers, J. J. (2016, April). Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors. In 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, April 17-20, 2016. | Publication | FY2016 |
| Rebak, R. B., Huang, S., Schuster, M., Buresh, S. J., & Dolley, E. J. (2019, July). Fabrication and mechanical aspects of using FeCrAl for light water reactor fuel cladding. Paper PVP2019-93128 presented at the PVP ASME Conference, San Antonio, TX. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Dolley, E. J. (2018, September 30-October 4). Assessing the electrochemical behavior of ferritic FeCrAl in high temperature water. Paper A0053 presented at TopFuel 2018, Prague, European Nuclear Society. | Publication | FY2019 |
| Rebak, R. B., Jurewicz, T. B., & Kim, Y.-J. (2019). Electrochemical behavior of accident tolerant fuel cladding materials under simulated light water reactor conditions. In ASTM STP 1609: Advances in electrochemical techniques for corrosion monitoring (pp. 231-243). | Publication | FY2019 |
| Richardson, M. D., Helmreich, G. W., Raftery, A. M., & Nelson, A. T. (2019). Resolution capabilities for measurement of fuel swelling using tomography (Report No. ORNL/SPR-2019/1071). Oak Ridge National Laboratory. | Publication | FY2019 |
| Schley, R. S., Hurley, D. H., Hua, Z., & Reese, S. J. (2019, February 9-14). In-pile instrument to measure changes in grain microstructure. In Proceedings of Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2019) (pp. 1135-1142), Orlando, FL. | Publication | FY2019 |
| Rebak, R. B., Terrani, K. A., & Fawcett, R. M. (2016). FeCrAl alloys for accident tolerant fuel cladding in light water reactors. In Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, Volume 6B: Materials and Fabrication, Vancouver, British Columbia, Canada, July 17-21, 2016 (Paper No. PVP2016-63162, V06BT06A009). ASME. | Publication | FY2016 |
| Schuster, M., Dolley, E. J., Jurewicz, T. B., & Rebak, R. B. (2019, August 18-22). Environmental degradation resistance of ATF FeCrAl cladding tube specimens during the fuel cycle. In Proceedings of the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 331-338), Boston, MA. | Publication | FY2019 |
| Seibert, R. L., Burns, J. R., Kiggans, J. O., & Terrani, K. A. (2019). Fabrication of fully ceramic microencapsulated compacts for miniature fuel specimen irradiation. Transactions of the American Nuclear Society, 121(1), 741-743. | Publication | FY2019 |
| Seibert, R. L., Kiggans, J. O., & Terrani, K. A. (2019, April). Fabrication of fully ceramic microencapsulated fuel pellets for HFIR irradiation (Report No. ORNL/SPR-2019/1133). Oak Ridge National Laboratory. | FY2019 | |
| Seibert, R. L., Terrani, K. A., Kiggans, J. O., McMurray, J. W., Jolly, B. C., Petrie, C. M., & Nelson, A. T. (2019, January). Fabrication and irradiation test plan for fully ceramic microencapsulated fuels (Report No. ORNL/TM-2019/1088). Oak Ridge National Laboratory. | Publication | FY2019 |
| Taller, S., Jiao, Z., Field, K., & Was, G. S. (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiation. Journal of Nuclear Materials, 527, 151831. | Publication | FY2019 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. (in submission). Temperature-dependent crystal structure of U3Si2 by high temperature neutron diffraction. Acta Materialia. | FY2019 | |
| Vogel, S. C., Wilson, T. L., & White, J. T. (2018, August 17). Crystal structure evolution of U-Si nuclear fuel phases as a function of temperature (Report No. LA-UR-18-28584). Los Alamos National Laboratory. | Publication | FY2019 |
| Vogel, S. C., Wilson, T. L., Wood, E. S., White, J. T., & Besmann, T. M. (2019, September 22-27). Temperature-dependent crystal structure of U3Si2 by high-temperature neutron diffraction. In Global 2019 Proceedings (pp. 1062-1069), Seattle, WA. | Publication | FY2019 |
| Williams, W. J., Hale, C., Sikik, E., Sprenger, M., Borghmans, G., Wachs, D. M., Van den Berghe, S., Okuniewski, M. A., Maddock, T., & Boer, B. (2019). Thermal-hydraulics and neutronics overview of the DISECT experiment. Transactions of the American Nuclear Society, 120(1), 348-351. | Publication | FY2019 |
| Williams, W. J., Wachs, D. M., Okuniewski, M. A., & van den Berghe, S. (2020). Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT). Annals of Nuclear Energy, 136, 107016. | Publication | FY2019 |
| Wilson, T. L., Besmann, T. M., Vogel, S. C., & White, J. T. (2019). Crystal structure characterization of uranium-silicides accident tolerant fuel by high temperature neutron diffraction. In Advances in X-ray Analysis (Vol. 63). Proceedings of the 68th Denver X-ray Conference, Volume 63, Lombard, Illinois, U.S.A., August 5-9, 2019. | Publication | FY2019 |
| Wood, E. S., Moczygemba, C., Robles, G., Nesloney, S., Grote, C., Cai, L., Xu, P., & Lahoda, E. (2019, September). Fabrication and steam oxidation testing of alloyed uranium silicide fuels. Submitted to TopFuel 2019, Seattle, WA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., & Snow, S. (2018). New capabilities for in-pile separate effects tests in TREAT. In Transactions of the American Nuclear Society Summer Meeting, Philadelphia, PA. | FY2019 | |
| Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), [Special issue on restarting transient reactor test facility]. | Publication | FY2019 |
| Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., & Tsai, K. (2019, June 9-13). Overview of I2 irradiation deployment activities in TREAT. In Proceedings of the American Nuclear Society Annual Meeting, 120(1), 280-282. | Publication | FY2019 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT. Annals of Nuclear Energy, 140, 107117. | Publication | FY2019 |
| Wozniak, N. R., White, J. T., Nolen, B. P., & Wermer, J. R. (2019, February 22). Assessment of feedstock synthesis routes for high density fuels (Report No. FT-19LA02020102). | FY2019 | |
| Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion behaviors between metallic fuel alloys with Pd addition and Fe. Journal of Nuclear Materials, 525, 111-124. | Publication | FY2019 |
| Yeom, H., Dabney, T., Johnson, G., Maier, B., & Sridharan, K. (2019). Oxidation of cold spray Cr coatings in high temperature steam environments. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 383-386. | Publication | FY2019 |
| Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019). Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels. Scripta Materialia, 162, 460-464. | Publication | FY2019 |
| Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O'Brien, R. C., & Wachs, D. M. (2016, May 15). TREAT irradiation vehicle designs, capabilities, and future plans. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, May 1-5, 2016. | FY2016 | |
| Zhong, W., Mouche, P. A., Han, X., Heuser, B. J., Mandapaka, K. K., & Was, G. S. (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions. Journal of Nuclear Materials, 470, 327-338. | Publication | FY2016 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | FY2017 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA's Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea, September 2017 | FY2017 | |
| Miao, Y., Harp, J., Mo, K., Bhattacharya, S., Baldo, P., & Yacout, A. M. (2017). Short communication on "In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures". Journal of Nuclear Materials, 484, 168-173. | Publication | FY2017 |
| Miao, Y., Harp, J., Mo, K., Zhu, S., Yao, T., Lian, J., & Yacout, A. M. (2017). Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C. Journal of Nuclear Materials, 495, 146-153. | Publication | FY2017 |
| Raiman, S., Doyle, P., Ang, C., & Terrani, K. (2017). Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (pp. 1475-1483). | Publication | FY2017 |
| Roth, M., Vogel, S. C., Bourke, M. A. M., Fernandez, J. C., Mocko, M. J., Glenzer, S., Leemans, W., Siders, C., & Haefner, C. (2017, April 19). Assessment of laser-driven pulsed neutron sources for poolside neutron-based advanced NDE-pathway to LANSCE-like characterization at INL (LA-UR-17-23190). | Publication | FY2017 |
| Sooby Wood, E., White, J. T., & Nelson, A. T. (2017). Oxidation behavior of U-Si compounds in air from 25 to 1000 °C. Journal of Nuclear Materials, 484, 245-257. | Publication | FY2017 |
| Zapata-Solvas, E., Hadi, M. A., Horlait, D., Parfitt, D. C., Thibaud, A., Chroneos, A., & Lee, W. E. (2017). Synthesis and physical properties of (Zr1-x,Tix)3AlC2 MAX phases. Journal of the American Ceramic Society, 100, 3393-3401. | Publication | FY2017 |
| Muta, H., Kurosaki, K., Uno, M., & Yamanaka, S. (2008). Thermal and mechanical properties of uranium nitride prepared by SPS technique. Journal of Materials Science, 43, 6429-6434. | Publication | FY2018 |
| Rebak, R. B. (2018). Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors. JOM, 70, 176-185. | Publication | FY2018 |
| Rebak, R. B., Gupta, V. K., & Larsen, M. (2018). Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C. JOM, 70, 1484-1492. | Publication | FY2018 |
| Yeom, H., Dabney, T., Johnson, G., & others. (2019). Improving deposition efficiency in cold spraying chromium coatings by powder annealing. International Journal of Advanced Manufacturing Technology, 100, 1373-1382. | Publication | FY2018 |
| Yeom, H., Maier, B., Johnson, G., Dabney, T., Walters, J., & Sridharan, K. (2018). Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™. Journal of Nuclear Materials, 507, 306-315. | Publication | FY2018 |
| Zalkin, A., & Templeton, D. H. (1953). The crystal structures of CeB4, ThB4, and UB4. Acta Crystallographica, 6(3), 269-272. | Publication | FY2018 |
| Kilby S.M, Marshall M.A, Choe D.O. et al. (2024). Design of Mini-Plate-1 Irradiation Test for Qualification of High-Density, Low-Enriched U-10Mo Monolithic Fuel. JOM. | Publication | FY2025 |
| Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C. & M. Tippet (2024). Fast Neutron Irradiation Capability in Existing Thermal Test Reactors, Annals of Nuclear Energy, Volume 207, 110731, ISSN 0306-4549. | Publication | FY2025 |
| Wang, Y., Burns, J., Yao, T. & L. Capriotti (2024). Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155209, ISSN 0022-3115. | Publication | FY2025 |
| Wang, Y., Howard, C., Xu, F., Salvato, D., Bawane, K., Murray, D., Frazer, D., Anderson, S., Yao, T., Yeo, S., Kim, J-H, Lee, B-O, Kim, J., Fielding, R. & L. Capriotti (2024). Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel, Journal of Nuclear Materials, Volume 599, 2024, 155231, ISSN 0022-3115. | Publication | FY2025 |
| Nicodemo G., Zullo G., Cappia F., Van Uffelen P., De Lara A., Luzzi L. & D. Pizzocri (2024). Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity. Journal of Nuclear Materials. 601:155301. | Publication | FY2025 |
| Colldeweih A., P. Petersen, M. Matos, J. Stockwell, R. Hansen, D. Kamerman, D. Lutz & F. Cappia (2025) Post irradiation examinations of FeCrAl cladding in PWR conditions Journal of Nuclear Materials Vol. 603, 155402 | Publication | FY2025 |
| Dabney, T., Sasidhar, K.N., Willing, E., Lukas, C., Quillin, K., Yeon, H. & K. Sridharan (2025). Microstructural Evolution in Ion Irradiated Cold Spray Cr Coated Zr-alloy, Journal of Nuclear Materials, vol. 606, 155652 | Publication | FY2025 |
| Chen, D., Burns, J., Wright, K. E., Salvato, D., Yao, T. & L. Capriotti (2025). Transmission electron microscopy characterization of fuel cladding chemical interaction between minor actinides bearing U-Pu-Zr fuel and AIM1 cladding. Journal of Nuclear Materials, 607, 155667. | Publication | FY2025 |
| Kancharla R.R, Chuirazzi W.C, Kane J.J et al. (2025). X-ray computed tomography of deconsolidated TRISO particles from the AGR-5/6/7 irradiation experiment capsule 1 compact. J Nucl Mater. ; 607:155704. doi:10.1016/j.jnucmat.2025.155704. | Publication | FY2025 |
| Meehan N.A., Gorton J.P., Capps N.A. & N.R. Brown (2025). Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions. Journal of Nuclear Materials, 2025;609:155745. doi:10.1016/j.jnucmat.155745. | Publication | FY2025 |
| Middlemas, S., & C. Adkins (2025). A critical analysis of U-Pu-Zr phase transitions using calorimetric, microstructural, and phase equilibria data. Journal of Nuclear Materials, 612, 155778. | Publication | FY2025 |
| Probert A., Swearingen A., Schulthess J., Capriotti L., Jensen C. & A. Aitkaliyeva (2025). Comparative Post-irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Steady-state Irradiation Behavior Against Historical and Modeled Fuel Performance. Journal of Nuclear Materials.; 610:155782. | Publication | FY2025 |
| Dhulipala, S. L. N., Simon, P.-C. A., Demkowicz, P. A., Hirschhorn, J. A. & S. R. Novascone (2025). Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches. Journal of Nuclear Materials, 610, 155795. | Publication | FY2025 |
| Salvato, D., Nguyen, B.-P., Wang, Y., Di Lemma, F. G., Capriotti, L., Aitkaliyeva, A. & T. Yao, (2025). TEM Characterization of Two Variants of Fuel Cladding Chemical Interaction in a HT-9 Clad U-10Zr Fuel. Variant 1: FCCI with a Zr Rind. Journal of Nuclear Materials, 614, 155855. | Publication | FY2025 |
| Espersen, J. I., Garrison, B. E., Cervenka, P., Seshadri, A., Linton, K., Shirvan, K., Capps N.A & N.R. Brown (2025). The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions. Journal of Nuclear Materials, 155910. | Publication | FY2025 |
| Skerjanc, W. F., Jiang, W., Demkowicz, P. A. & J.D. Stempien (2025). Evaluation of AGR-3/4 In-pile Silver Release Predictions Against Post-irradiation Examination measurements. Journal of Nuclear Materials, 615, 155942. | Publication | FY2025 |
| Mauseth, T., Dunzik-Gougar, M. L. & F. Teng (2025). Micro-tensile Characteristics of As-fabricated and Irradiated AGR-2 TRISO Fuel Particle Buffer, IPyC, and Buffer-IPyC Interlayer Regions. Journal of Nuclear Materials, 156086. | Publication | FY2025 |
| Capriotti, L., Di Lemma, F., Salvato, D., Xu, F., Tang, Y., Paaren, K.M., Swearingen, A.L., Jensen, C.B., Wang, Y. & D.L. Porter (2025). An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in HT9/U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis. Journal of Nuclear Materials, p.156092. | Publication | FY2025 |
| Pradhan A, Xu F, Salvato D, et al. (2024). Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning. Mater Charact. 2024;218(1):114524. | Publication | FY2025 |
| Rittenhouse J., Pradhan A., Kamerman D.W, Burns J., Xu F., Wen H. & T. Yao (2025) Site-specific Nanoscale Characterization of Zirconium Hydrides in the Hydride Rim Structure of Hydrogen-charged Zircaloy-4 Cladding. Mater Charact ;224:115006. | Publication | FY2025 |
| Yang, G., Nguyen, B.-P., Rittenhouse, J. E., Xu, F., Gonderman, S., Gazza, J., Xu, P. & T.Yao (2025). Investigating Grain Structure and Microcracking in SiCf-SiCm Composites Using 4D-STEM. Materials Characterization, 225, 115165. | Publication | FY2025 |
| Zhao, L., Xu, F., Porter, D. L. & Y. Wang (2025). Quantification of line dislocations in FFTF irradiated HT9 cladding by deep learning method. Materials Characterization, 227, 115322. | Publication | FY2025 |
| Beausoleil, G. L., Curnutt, B., Moorehead, M. & Bascom, A. (2025). Multi-principal element alloys for fast reactor cladding applications. Nuclear Engineering and Technology, 57(4), 103303. | Publication | FY2025 |
| Chuirazzi, W., Bush, J., Gross, B., Bryant, M., Clark, K., Cook, M., Burtenshaw, J., Price, J., Morankar, S., Blattner, M., Landon, R., Galloway, K., Stanger, J., Stamos, R., Duke, J., Watt, C. & J. Stempien (2025). Strategy to safely enable X-ray computed tomography examination of highly radioactive tristructural isotropic nuclear fuel. Nuclear Engineering and Technology, 57(10), 103726. | Publication | FY2025 |
| Seo S., Folsom C., Jensen C. et al. (2024). International Fuel Performance Study of Fresh Fuel Experiments for PCMI Effects During RIA Experiments. Nuclear Engineering and Design; 430:113673. | Publication | FY2025 |
| Moussaoui, M. A., Anderson, K. S., Yoo, J., & N.E. Woolstenhulme (2025) Device for steam cladding oxidation testing at TREAT, Nuclear Engineering and Design, 445, 114441. | Publication | FY2025 |
| Downey C.M., Oldham N., Fleming A., Chapman D., Mata Cruz A. & K. Ellis (2024). Design of a First-of-a-kind Instrumented Advanced Test Reactor Irradiation Capsule Experiment for in Situ Thermal Conductivity Measurements of Metallic Fuel. Prog Nucl Energy.;175:105325. | Publication | FY2025 |
| Umretiya, R.V, Qu, H., Yin, L., Jurewicz, T.B., Gupta, V.K., Drobnjak, M., Knussman, M. Hoffman, A.K. & R.B. Rebak (2024). Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments, npj Mater Degrad 8, 88. | Publication | FY2025 |
| Zhao, L., Wang, Y., & F. Xu (2025). Accurate Segmentation of Localized Fuel Cladding Chemical Interaction Layers in SEM Micrographs with Deep Learning Method. Scientific Reports, 15, 28878. | Publication | FY2025 |
| Chavez, R., Anand, N.K. & Hassan, Y. & S. Girimaji (2024) "Flow Over a Sphere at Elevated Pressures: An Analysis of the Near-Wake Using Spectral Proper Orthogonal Decomposition" Physics of Fluids, November 2024, Vol. 36, 115155 (1-17) Issue 11, selected as Editors Pick. | Publication | FY2025 |
| Hawkes, G., Pham, B. & C. Otani (2024). Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps. Nuclear Science and Engineering, 126. | Publication | FY2025 |
| Riet, A. A. & J.D. Stempien (2025). Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation. Nuclear Science and Engineering, 112. | Publication | FY2025 |
| Petersen, P. G., Hansen, R. S., Cappia, F., Kamerman, D., Baird, K. & C. Christensen (2024). Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens. Journal of Testing and Evaluation, 52(6), 33263345. | Publication | FY2025 |
| Capps, N., Yan, Y., Harp, J., Ridley, M. & R. Salko Jr. (2024). Recent High Burnup LOCA Testing at Oak Ridge National Laboratory (ORNL/SPR-2024/3544). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Singh G., Yu J., Xu F., Yao T. & P. Xu (2024). Multiscale Modeling of Silicon Carbide Cladding for Nuclear Applications: Thermal Performance Modeling. Energies. 2024; 17(23):6124. | Publication | FY2025 |
| Cakmak, E., Cinbiz, M. N., Arregui-Mena, J. D., Deck, C. & T. Koyanagi (2025). Damage Progression and Failure of SiC/SiC Composite Tubes under Hard-Contact Radial Expansion. Composites Part B: Engineering, 112869. | Publication | FY2025 |
| Dolley, E. J., Zhang, W., Zorn, G., Sand, T. & R.B. Rebak (2024) "Enhanced mechanical properties and wear resistance of FeCrAl alloys at~ 300 C and Higher temperatures." JOM 76, no. 8 (2024): 4123-4130. | Publication | FY2025 |
| Nagothi, B.S., Qu, H., Zhang, W., Umretiya, R.V., Dolley, E.& R.B. Rebak (2024). "Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding." Materials 17, no. 7: 1633. | Publication | FY2025 |
| Qu, H., Yin, L., Larsen, M., and R.B. Rebak (2024). "Distinctive oxide films develop on the surface of fecral as the environment changes for nuclear fuel cladding." Corrosion and Materials Degradation 5, no. 1: 109-123. | Publication | FY2025 |
| Woolstenhulme, N. et al. (2025). SPARC - Plans for a New Critical Experiment Facility with a Horizontal Split Table (INL/RPT-25-84855). Idaho National Laboratory, Idaho Falls, ID. | Publication | FY2025 |
| Yang, Y., Weicheng Z. & C. Massey (2025). Computational Design of Improved Fast Reactor Cladding (ORNL/TM-2025/3953), Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., Laug, D.V. & J.D. Stempien (2024). Micro-tensile Properties of Fueled Irradiated AGR-2 TRISO-coated Particle Buffer, IPyC, and SiC Interlayer Regions. Presented at the 2024 Nuclear Materials (NuMat) Conference. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L. & J.D. Stempien (2024). Micro-Tensile Properties of Irradiated AGR-2 TRISO Fuel Pyrolytic Carbon (PyC) and Silicon Carbide (SiC) Coatings. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Teng, F., Cai, L., & J.D. Stempien (2024). Fracture Behavior Considerations for the TRISO Particle Matrix. Presented at the 2024 Workshop on Storage and Transportation of TRISO and Metal Spent Nuclear Fuels. | Publication | FY2025 |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles. Presented at the 2025 Nuclear Science User Facilities (NSUF) Annual Program Review. | Publication | FY2025 |
| Qu, H.J., Chikhalikar, A.S., Abouelella, H., Roy, I., Rajendran, R., Nagothi, B.S., Umretiya, R., Hoffman, A.K. & R.B. Rebak (2024). "Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments." Corrosion Science 229 (2024): 111870. | Publication | FY2025 |
| Roy, R., Chatterjee, A., Mondal, S., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya.(2025). "Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions." Corrosion Science: 112965. | Publication | FY2025 |
| Mondal, S., Chatterjee, A., Roy, R., Muntaha, M.A., Wharry, J.P., Qu, H.J. & R. Umretiya. "Synergistic Roles of Cr and Mo in Low Temperature Steam Oxidation of FeCrAl Alloys." Corrosion Science (2025): 113107. | Publication | FY2025 |
| Rajendran, R., Chikhalikar, A.S., Roy, I., Abouelella, H., Qu, H.J., Umretiya, R.V., Hoffman, A.K., and R.B. Rebak (2024). "Effect of aging and ?segregation on oxidation and electrochemical behavior of FeCrAl alloys." Journal of Nuclear Materials 588: 154751. | Publication | FY2025 |
| Joyce, L., Wang, P., Umretiya, R.V., Hoffman, A. & Y. Xie (2024). "Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water." Journal of Nuclear Materials 593: 154987. | Publication | FY2025 |
| Chikhalikar, A.S., Qu, H., Abouelella, H., Nagothi, B., Rajendran, R., Roy, I., Umretiya, R., Hoffman, A. & R. Rebak, . "Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys." Journal of Nuclear Materials 598 (2024): 155179. | Publication | FY2025 |
| Nelson M., Samuha S., Kombaiah B., Kamerman D. & P. Hosemann (2024). Enhanced Stress Relaxation Behavior Via Basal ?a?dislocation activity in Zircaloy-4 cladding. Journal of Nuclear Materials ;601:155337. | Publication | FY2025 |
| Hirschhorn J.A., Aagesen L.K., Jiang C. & G.L. Beausoleil (2025). Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels. Nucl Eng Des ;432:113811. | Publication | FY2025 |
| Ravi, S.K., Comlek, Y., Pathak, A., Gupta, V., Umretiya, R., Hoffman, A., Pilania, G. et al. (2025) "Interpretable multi-source data fusion through Latent Variable Gaussian Process." Engineering Applications of Artificial Intelligence 145: 110033. | Publication | FY2025 |
| Umretiya, R.V., Chikhalikar, A., Elward, B., Moreira, T.A., Anderson, M., Rebak, R.B. & J.V. Rojas (2024). "The Effect of Ramp Heating on the Microstructure and Surface Chemistry of APMT FeCrAl Alloy." Nuclear Materials and Energy 38: 101567. | Publication | FY2025 |
| Joyce, L., Umretiya, R.V., Qu, H., Shang, Z. & Y. Xie (2025). "Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400900° C." Nuclear Materials and Energy : 101953. | Publication | FY2025 |
| Bermudez, S., Erdogan, F., Davis, V., Rojas, J.V. & R.V. Umretiya (2025). "Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000° C)." Nuclear Materials and Energy : 101972. | Publication | FY2025 |
| Bawane, K.K., Yang, G., Yao, T., Xu, F., Xu, P., Gonderman, S. & J. Gazza (2025). Microstructure Analysis of Silicon Carbide Cladding Using 4D-STEM. Paper presented at M&M 2025. | FY2025 | |
| Cappia F., Colldeweih, A., Frazer, D., Hansen, R., Petersen, P., Stockwell, J., Anderson, S., Charbeneau, J., Kamerman, D. (2024) Effect of Metal Contaminants on Cr Coating Performance after Irradiation in the Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Carvajal, J. (2025). In-Rod Sensor System Irradiation Test Results with Segmented Fuel Assembly, accepted for the 14th International Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2025), Chicago. | FY2025 | |
| Cervenka, P., Seshadri A., Sevecek M., Cvrcek L. & K. Shirvan (2024). Development of PVD Cr-(Nb) coated fuel cladding with enhanced accident tolerance, Presented at the Nuclear Materials Conference. | FY2025 | |
| Chavez, R. (2025). Fluid Dynamics and Thermal Effects of Flow Over a Sphere at High Pressures and Graphitic Dust Behavior in Square Channels, PhD Dissertation, Texas A&M University. | FY2025 | |
| Chavez, R., Anand, N.K. & Y. Hassan (2025) High-Pressure Experimental Analysis of Thermal Effects on Near-Wake Turbulence and Energy Distribution of Flow over a Heated Sphere, Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Colldeweih A., Kamerman, D., Matos, M., Bawane, K., J. Stockwell, J., A. Pradhan, A., Hansen, R., Cappia, F. & D. Lutz (2024) Corrosion of Neutron Irradiated FeCrAl in the ATR Water Loop TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Dabney, T., Sasidhar, K.N., Willing, E., Eftink, B., Li, N., Maier, B., Walters, J. & K. Sridharan (2025). Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding, Symposium on Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Hansen R., Colldeweih, A., Petersen, P., Stockwell, J., Charboneau, J., Albuquerque, L., Baird, K., Kamerman, D. & F. Cappia (2024) Examinations of Cr-Coated M5 Cladding Irradiated at the INL Advanced Test Reactor TopFuel 2024 Conference Proceeding. Grenoble, France. | FY2025 | |
| Harp, J., Yan, Y., Morris, R., Baldwin, C., Jones, M. & N. Capps (2024). Development of Fission Gas Release Cabilities to Study High Burnup Commercial Fuel Performance under Loss of Coolant Accident Conditions. Proc. TopFuel 2024, Grenoble, France. | FY2025 | |
| Jung, W., Dunbar, C., Jo, J.Y., Sridharan, K. & H. Yeom (2025). Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr cladding under Multiple Quench Tests, Symposium on Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Karlsson, T. Y. (2025). Fuel Qualification: Near-Term Activities & Needs for Molten Salt Fuels. Presented at the EPRI Advanced Reactor Workshop. | FY2025 | |
| Kosmidou, M., Broussard, A., Lian, J. & E. Kardoulaki (2025). Filling of data gaps for the development of ceramic fuels, pp. 23.Materials in Nuclear Energy Systems (MiNES) 2025 Conference. | FY2025 | |
| Li, N., Xie, D., Kim, H., Dabney, T., Eftink, B., Sridharan, K., Graening, T., Nelson, A., Fensin, S.& S. Maloy (2025). In Situ Micro-Cantilever Beam Bending Tests to Assess the Adhesion Strength of Cr Coatings on Zry-4, Symposium on Mechanical Behavior Related to Interface Physics IV, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Mauseth, T. J., Dunzik-Gougar, M. L., Teng, F., Shah, S., Bawane, K. K., Pradhan, A., Cai, L., Bachhav, M. & J.D. Stempien (2025). Microstructural Characterization of AGR-2 TRISO Particle Buffer, IPyC, and Buffer-IPyC Interfaces. Presented at the 2025 Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). | FY2025 | |
| Pham, B. T., Hawkes, G. L., Lybeck, N. J., Otani, C. & P.A. Demkowicz (2025). Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment. Paper presented at the NURETH 21 Annual Meeting. | FY2025 | |
| Seshadri A., Cervenka P., Fazi A., Sevecek M., Carpenter D., Cetiner N., Motta A., Ishak C., Fei Z., Raiman S., Xu P. & K. Shirvan. In-pile hydrothermal corrosion behavior of Zirconium Alloys with and without ATF Coatings, Presented at 21st ASTM International Symposium on Zirconium in the Nuclear Industry. | FY2025 | |
| Shirvan K., Cervenka P., Fazi A. & A. Seshadri (2025). Experimental Investigation of CrNb Coatings for PWRs and BWRs. Paper at the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. | FY2025 | |
| Sridharan, K. Maier, B., Dabney, T., Willing, E., Pocquette, N. Lukas, C., Anderson, N. & H. Yeom (2025). Cold Spray Materials Deposition Technology for Nuclear Energy Systems, Symposium on Advances in Materials Deposition by Cold Spray and Related Technologies, The Metallurgical Society (TMS) Annual Conference, Las Vegas, NV, March 2025. | FY2025 | |
| Walter, J., Roberts, E., Fredrick, K., Viands, D. & X. Huang (2025). The Effect of Chromium Coating Microstructure and Oxide Films on Hydrogen Uptake in Zirconium-alloy Nuclear Fuel Cladding, 21st International Symposium on Zirconium in the Nuclear Industry, Aix-en-Provence, France. | FY2025 | |
| Woolstenhulme, N., Martin, N., DeHart, M., Percher, C., Cutler, T., Wieselquist, W. (2025). SPARC, an Effort to Reestablish a Horizontal Split Table Critical Facility for HALEU Experiments and Beyond. Paper presented at the NCSD 2025 Annual Meeting. | FY2025 | |
| Yuan, G., Cook, D.H., Barnard, H., Lahoda, E., Xu, P., Ritchie, R.O. & D. Liu (2025). Improved Damage Tolerance of SiC-Based Nuclear Fuel Cladding with Novel Multi-Layered SiC Coating Design at 1200°C, Materials & Design, Volume 256, August 2025, 114260. | Publication | FY2025 |
| Zhang, S., Ma, Z., Xu, P. (2024). Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors, 2024 ANS Annual Meeting. | FY2025 | |
| Zhang, J., Xu, P., Sevecek, M., Sim, K.S. & A. Khaperskaia (2025). Contribution of IAEA Coordinated Research Projects to Light Water Reactors Advanced Technology Fuel Testing and Simulation, Nuclear Engineering and Design 418, 112910. | Publication | FY2025 |
| Reference | Link | Year |
|---|---|---|
| Anderson KS, Hale DD, Schulthess JL, Arrowood MM. A standard capsule design for structural material testing in the Advanced Test Reactor. Nucl Eng Des. 2023;414:112630. | Publication | FY2024 |
| Beck PM, Hayne ML, Liu C, Valdez J, Nizolek T, Briggs SA, Maloy SA, Saleh TA, Eftink BP. Mandrel diameter effect on ring-pull testing of nuclear fuel cladding, J Nucl Mater. 2024;596:155087. | Publication | FY2024 |
| Folsom CP, Schulthess JL, Kamerman DW, et al. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. | Publication | FY2024 |
| Gribok AV, Di Lemma FG, Fay J, Porter DL, Paaren KM, Capriotti L. Qualification and Quantification of Porosity at the Top of the Fuel Pins in Metallic Fuels Using Image Processing. Energies. 2024; 17(9):1990. | Publication | FY2024 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. | Publication | FY2024 |
| Hu C, Le J-L, Koyanagi T, Labuz JF. Experimental investigation of probabilistic failure of SiC/SiC composite tubes under multiaxial loading. Compos Struct. 2024;335:118002. | Publication | FY2024 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:07547. | Publication | FY2024 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. | Publication | FY2024 |
| Koyanagi T, Hawkins C, Lamm B, Lara-Curzio E, Katoh Y, Deck C. Mechanical degradation of duplex SiC-fiber reinforced SiC matrix composite tubes under a controlled high-temperature steam environment. Ceram Int. 2024. | Publication | FY2024 |
| Koyanagi T, Hu X, Petrie CM, Singh G, Ang C, Deck CP, Kim W-J, Kim D, Sauder C, Braun J, Katoh Y. Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux. J Nucl Mater. 2024;588:154784. | Publication | FY2024 |
| Lu C, Kardoulaki E, Stauff NE, Cuadra A. The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nucl Technol. 2024:1-18. | Publication | FY2024 |
| Martin N, Seo S, Prieto SB, Jesse C, Woolstenhulme N. Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Prog Nucl Energy. 2023;165:104895. | Publication | FY2024 |
| Middlemas S, Janney DE, Adkins C, Bawane K. Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys. J Nucl Mater. 2024;591:154909. | Publication | FY2024 |
| Nelson M, Samuha S, Kamerman D, Hosemann P. Temperature-Dependent Mechanical Anisotropy in Textured Zircaloy Cladding. J Nucl Mater. | Publication | FY2024 |
| Paaren KM, Christian S, Capriotti L, Aitkaliyeva A, Porter D. Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination. Energies. 2023;16(19):6817. | Publication | FY2024 |
| Paaren K, Gale M, Wootan D, Medvedev P, Porter D. Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data. Energies. 2023;16:7600. | Publication | FY2024 |
| Patnaik S, Beausoleil II GL, Capriotti L. Fission accelerated steady-state post irradiation examinations Part II. Nucl Eng Technol. 2024. | Publication | FY2024 |
| Salvato D, Paaren KM, Hirschhorn JA, Aagesen LK, Xu F, Di Lemma FG, Capriotti L, Yao T. The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study. J Nucl Mater. 2024;591:154928. | Publication | FY2024 |
| Terricabras AJ, Drewry SM, Campbell K, et al. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2. J Nucl Mater. 2024;594:155022. | Publication | FY2024 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. | Publication | FY2024 |
| Worrall M, Woolstenhulme N, Downey C, Jesse C, Murdock C, Tippet M. Fast neutron irradiation capability in existing thermal test reactors. Ann Nucl Energy. | Publication | FY2024 |
| Xu F, Yao T, Xu P, et al. Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies. 2024;17(1):197. | Publication | FY2024 |
| Yan Y, Harp J, Le Coq A, Massey C, Linton K. High-temperature steam oxidation study of irradiated FeCrAl defueled specimens. Journal of Nuclear Materials. 2024 Mar 1;590:154868. | Publication | FY2024 |
| Beausoleil G, Capriotti L, Curnutt B, Fielding R, Hayes S, Wachs D. FAST irradiations and initial post irradiation examinations Part I. Nucl Eng Technol. 2022;54(11):4084-4094. ISSN 1738-5733 | Publication | FY2023 |
| Benson MT, Yao T, Zelina JN, Teng F, Murray D, Di Lemma F, Williams WJ, Zhang J, Zhuo W. The formation mechanism of the Zr rind in U-Zr fuels. J Nucl Mater. 2022;572:154057. ISSN 0022-3115. | Publication | FY2023 |
| Cappia F, Wright K, Frazer D, Bawane K, Kombaiah B, Williams W, Finkeldei S, Teng F, Giglio J, Cinbiz MN, Hilton B, Strumpell J, Daum R, Yueh K, Jensen C, Wachs D. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing. J Nucl Mater. 2022;569:153881. ISSN 0022-3115. | Publication | FY2023 |
| Capriotti L, Di Lemma FG, Harp JM. Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy. J Nucl Mater. 2023;575:154221. ISSN 0022-3115. | Publication | FY2023 |
| Di Lemma FG, Yao T, Salvato D, Capriotti L, Teng F, Jokisaari AM, Beeler BW, Wang Y, Jensen CJ. Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics. J Nucl Mater. 2023;577:154341. ISSN 0022-3115. | Publication | FY2023 |
| Folsom CP, Armstrong RJ, Woolstenhulme NE, Fleming AD, Hill CM, Jensen CB, Wachs DM. Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility. Nucl Eng Des. 2022;397:111919. ISSN 0029-5493. | Publication | FY2023 |
| Folsom CP, Schulthess JL, Kamerman DW, Hansen RS, Woolstenhulme NE, Jensen CB, Astle LA, Giraldo LO, Fleming A, Wachs DM. Resumption of water capsule reactivity-initiated accident testing at TREAT. Nucl Eng Des. 2023;413:112509. ISSN 0029-5493. | Publication | FY2023 |
| Hansen RS, Kamerman DW, Petersen PG, Cappia F. Evaluation of the ring tension test (RTT) for robust determination of material strengths. Int J Solids Struct. 2023;282:112471. ISSN 0020-7683. | Publication | FY2023 |
| Hanson WA, Cappia F, White JT, McClellan KJ, Harp JM. Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels. J Nucl Mater. 2023;578:154346. ISSN 0022-3115. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic Modeling of Lifetime Distribution of SiC/SiC Composite Claddings. J Am Ceram Soc. December 2022. | Publication | FY2023 |
| Kamerman D, Bachhav M, Yao T, Pu X, Burns J. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. J Nucl Mater. 2023;586:154675. ISSN 0022-3115. | Publication | FY2023 |
| Kamerman D. The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads. Eng Fail Anal. 2023;153:107547. ISSN 1350-6307. | Publication | FY2023 |
| Kamerman D, Nelson M. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes. Nucl Technol. February 2023. | Publication | FY2023 |
| Kane K, Bell S, Capps N, Garrison B, Shapovalov K, Jacobsen G, Deck C, Graening T, Koyanagi T, Massey C. The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts. J Nucl Mater. 2023;574:154152. ISSN 0022-3115. | Publication | FY2023 |
| Koyanagi T, Karakoc O, Hawkins C, Lara-Curzio E, Deck C, Katoh Y. Stress rupture of SiC/SiC composite tubes under high-temperature steam. Int J Appl Ceram Technol. 2023. ISSN 1546-542X. | Publication | FY2023 |
| Hu C, Labuz JF, Koyanagi T, Le J-L. Mechanistic modeling of lifetime distribution of SiC/SiC composite claddings. J Am Ceram Soc. 2023;106:3066 3077. | Publication | FY2023 |
| Schulthess JL, Spencer BW, Petersen PG, Woolstenhulme NE, Ban D, Frazer D, Sudderth L, Hamilton S, Jewell JK, Mariani RD. Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. J Nucl Mater. 2023;574:154176. ISSN 0022-3115. | Publication | FY2023 |
| Wang Y, Miller BD, Harp JM, Salvato D, Capriotti L, Yao T. Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel. J Nucl Mater. 2022;572:153990. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Yao T, Pu X, Capriotti L. Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction. J Nucl Mater. 2023;585:154644. ISSN 0022-3115. | Publication | FY2023 |
| Williams WJ, Vogel SC, Okuniewski MA. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction. J Nucl Mater. 2023;579:154380. ISSN 0022-3115. | Publication | FY2023 |
| Woolstenhulme N, Chapman D, Cordes N, Fleming A, Hill C, Jensen C, Schulthess J, Ramirez M, Linton K, Schappel D, Vasudevamurthy G. TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project. J Nucl Mater. 2023;575:154204. ISSN 0022-3115. | Publication | FY2023 |
| Xu F, Cai L, Salvato D, et al. Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels. Sci Rep. 2023;13:10616. | Publication | FY2023 |
| Yan Y, Graening T, Nelson AT. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing. Metals. 2022;12(12):1998. | Publication | FY2023 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced Autonomous Welding for Refabrication and Follow-On Testing of Previously Irradiated Nuclear Fuel. Nucl Technol. 2023;209(2):127-143. | Publication | FY2023 |
| Yuan G, Forna-Kreutzer JP, Xu P, Gonderman S, Deck C, Olson L, Lahoda E, Ritchie RO, Liu D. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Mater Des. 2023;227:111784. ISSN 0264-1275. | Publication | FY2023 |
| Cocke, C.K., Rollett, A.D., Lebensohn, R.A. et al. The AFRL Additive Manufacturing Modeling Challenge: Predicting Micromechanical Fields in AM IN625 Using an FFT-Based Method with Direct Input from a 3D Microstructural Image, Integr Mater Manuf Innov Volume 10 (2021) 157 | Publication | FY2022 |
| Copeland-Johnson, T.M., Nyamekye, C.K.A., Ecker, L., Bowler, N., Smith, E.A., Rebak, R.B. & S. K. Gill. Analysis of Inconel 600 Oxidized under Loss-of-Coolant Accident Conditions: A Multi-modal Approach, Corrosion Science Volume 195 (2022) 109950, | Publication | FY2022 |
| Evans, K.J. & R. B. Rebak. Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding, Corrosion Journal, Volume 78 (May 2022) 449 | Publication | FY2022 |
| Garud, Y.S., Hoffman, A.K. & R. B. Rebak. Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review, Metallurgical and Materials Transactions A, | Publication | FY2022 |
| Hoffman, A. K., Cappia, F., Burns, J., He, L., Umretiya, R., Gupta, V., Massey, C., Harp, J.& R. B. Rebak. FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environment, in Transactions of the ANS Winter 2021 meeting, Washington DC, USA. December 2021 Volume 125 (2021) 515 | Publication | FY2022 |
| Huang, S., Dolley, E., An, K., Yu, D., Crawford, C., Othon, M.A., Spinelli, I., Knussman, M.P. & R. B. Rebak. Microstructure and Tensile Behavior of Powder Metallurgy FeCrAl Accident Tolerant Fuel Cladding, Journal of Nuclear Materials Volume 560 (2022) 153524 | Publication | FY2022 |
| Kane K, Bell S, Garrison B, Ridley M, Gussev M, Linton K, Capps N. Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method. J Nucl Mater. 2022;572:154063. | Publication | FY2022 |
| Kocevski, V., Cooper, M.W.D., Claisse, A.J., Andersson & D.A. Hide. Development and Application of a Uranium Mononitride (UN) Potential: Thermomechanical Properties and Xe Diffusion, Journal of Nuclear Materials, Volume 562 (April 2022) | Publication | FY2022 |
| Koyanagi, T. Wang, H., Arregui Mena, JD., Petrie, C.M., Deck, C.P., Kim, W-J., Kim, D., Sauder, D., Braun, J.& Y. Katoh. Thermal Diffusivity and Thermal Conductivity of SiC Composite Tubes: The Effects of Microstructure and Irradiation, Journal of Nuclear Materials, Volume 557 (December 2021) | Publication | FY2022 |
| Kumagai, T., Pachaury, Y., Maccione, R., Wharry, J.P & A. El-Azab. An Atomistic Investigation of Dislocation Velocity in Body-centered Cubic FeCrAl Alloys , Materialia Volume 18 (2021) 101165 | Publication | FY2022 |
| Liu, J. et al. Structural and Phase Evolution in U3Si2 During Steam Corrosion, Corrosion Science, Volume 204 (2022) 110373 | Publication | FY2022 |
| Macisaac, M. Bavdekar, S. Subhash, G. Nance, J. Sankar, B. V., Kim, N-H. & G. Subhash. A Novel Rotating Flexure-Test Technique for Brittle Materials with Circular Geometries, Experimental Techniques Volume 12 (2022) | Publication | FY2022 |
| Mirmohammad, H. & O. Kingstedt. Theoretical Considerations for Transitioning the Grid Method Technique to the Microscale, Exp Mech Volume 61 (2021) 753. | Publication | FY2022 |
| Mirmohammad, H., Gunn, T. & O.T. Kingstedt. In-Situ Full-Field Strain Measurement at the Sub-grain Scale Using the Scanning Electron Microscope Grid Method, Exp Tech Volume 45 (2021) 109. | Publication | FY2022 |
| Nagaraju, H. T., Subhash, G., Kim, N-H, Haftka, R.& B. Sankar. Effect of Curvature on Extensional Stiffness Matrix of 2-D Braided Composite Tubes, Composites Part A: Applied Science and Manufacturing Volume 147(2021) 106422 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Haftka, R., Kim, N-H, Deck, C. & S. Oswal. Measurement of Residual Stress in Silicon Carbide Fibers of Tubular Composites Using Raman Spectroscopy, Acta Materialia Volume 217(2021) 117164 | Publication | FY2022 |
| Nance J.R., Subhash, G. Sankar, B., Kim, N-H, Deck C. & S. Oswald. Influence of Weave Architecture on Mechanical Response of SiCf-SiCm Tubular Composites, Materials Today Communications Volume 33(2022) 104206 | Publication | FY2022 |
| Pachaury, Y., Kumagai, T., Wharry, J.P. & A. El-Azab. A Data Science Approach for Analysis and Reconstruction of Spinodal-like Composition Fields in Irradiated FeCrAl Alloys, Acta Materialia Volume 234 (2022) 118019 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., McFarland, M. & K. Sridharan. Experimental Evaluation of Direct Current Magnetron Sputtered and High-power Impulse Magnetron Sputtered Cr Coatings on SiC for Lightwater Reactor Applications, Thin Solid Films Volume 716 (2020) 138431 | Publication | FY2022 |
| Quillin, K., Yeom, H., Dabney, T., Willing, E. & K. Sridharan. Microstructural and Nanomechanical Studies of PVD Cr coatings on SiC for LWR Fuel Cladding Applications, Surface and Coatings Technology Volume 441 (2022) 128577 | Publication | FY2022 |
| Rebak, R.B. Innovative Accident Tolerant Nuclear Fuel Materials Will Help Extending the Life of Light Water Reactors, KOM Corrosion and Material Protection Journal Volume 66 (2022) 36. | Publication | FY2022 |
| Rebak, R.B., Dolley, E.J., Zhang, W., Umretiya, R.V. & A. K. Hoffman. Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels, In Proceedings of ASME 2022 PVP Conference, Las Vegas, US. July 2022, | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Hoffman, A.K., Yin, L., Amroussia, A., Umretiya, R.V. & R. M. Fawcett. Zinc Additions Reduces Dissolution Rate of FeCrAl Fuel Cladding, in Transactions of ANS Winter 2021 meeting, Washington DC, US. December 2021. Volume 125 (2021) 513. | Publication | FY2022 |
| Rebak, R.B., Jurewicz, T.B., Larsen, M. & L. Yi. Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding, Corrosion Science 198 (2022) 110156. | Publication | FY2022 |
| Rebak, R.B., Umretiya, R.V., Hoffman, A.K., Yin, L., Amroussia, A. & D. R. Lutz. Reprocessing Capabilities of FeCrAl-Clad Used Fuel, in Transactions of the ANS Winter 2021 meeting, Washington DC, December 2021, Volume 125 (2021) 181. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Jurewicz, T.B. & A. K. Hoffman. Acid Dissolution Behavior of Ferritic FeCrAl Tubes Candidates for Nuclear Fuel Cladding, Corrosion Journal, Volume 77 (2021) 1321. | Publication | FY2022 |
| Rebak, R.B., Yin, L., Larsen, M., Umretiya, R.V. & A. K. Hoffman. Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry, Paper PVP2022-80559 in Proceedings of ASME 2022 PVP Conference, July 2022, Las Vegas | Publication | FY2022 |
| Sankar, B. V., Thandaga Nagaraju, H., Kim, N-H. & G. Subhash. An Extrapolation Method to Remove Spurious Stress Concentration in Pixel-based Meshes, Composite Structures Volume 290 (2022) 115522 | Publication | FY2022 |
| Schoell, R., Kabel, J., Lam, S., Sharma, A., Michler, J., Hosemann, P. & D. Kaoumi. Corrosion Behavior of a Series of Combinatorial Physical Vapor Deposition Coatings on SiC in a Simulated Boiling Water Reactor Environment, Journal of Nuclear Materials (2022) | Publication | FY2022 |
| Smith, A. J., Maxwell, H. L., Mirmohammad, H., Kingstedt, O. T. & R.B. Berke. A Novel Variable Extensometer Method for Measuring Ductility Scaling Parameters from Single Specimens. ASME. J. Appl. Mech, Volume 89 (2022) 031006 | Publication | FY2022 |
| Sun T, Shang Z, Cho J, Ding J, Niu T, Zhang Y, Yang B, Xie D, Wang J, Wang H, Zhang X. Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability. Acta Materialia. 2021;215:117049. | Publication | FY2022 |
| Sun T, Cho J, Shang Z, Niu T, Ding J, Wang J, Wang H, Zhang X. Deformation mechanism in nanolaminate FeCrAl alloys by in situ micromechanical strain rate jump tests at elevated temperatures. Scripta Materialia. 2022;215:114698 | Publication | FY2022 |
| Warren, P., Warren, G., Wu, Y.Q., Burns, J., Dubey, M. & J.P. Wharry. Method for fabricating depth-specific TEM in situ tensile bars, JOM Volume 72 (2020) 2057 | Publication | FY2022 |
| Wei, B.Q., Xie, D.Y., Wu, W.Q. Shao, L & J Wang. Quantifying the Glide Resistance to Dislocations in Proton-Irradiated FeCrAl Alloy, JOM (2022) | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, Deciphering water-solid reactions during hydrothermal corrosion of SiC, Acta Materialia Volume 209 (2021) 116803 | Publication | FY2022 |
| Xi, J., Liu, C., Morgan, D. & I. Szlufarska, An unexpected role of H during SiC corrosion in water, Journal Phys. Chem. C, Volume 124 (2020) 9394 | Publication | FY2022 |
| Xie, D.Y., Wei, B., Wu, W.Q. & J Wang. Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars, Crystals Volume 10 (2020) 943 | Publication | FY2022 |
| Xu, S., Xie, D., Liu, G., Ming, K. & J Wang. Quantifying the resistance to dislocation glide in single phase FeCrAl alloy, International Journal of Plasticity Volume 132 (2020) 102770 | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties, Journal of Nuclear Materials Volume 557 (2021) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance, Journal of Nuclear Materials Volume 559 (2022) | Publication | FY2022 |
| Yang, K., Kardoulaki, E., Zhao, D., Gong, B., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J. & J. Lian, UN and U3Si2 Composites Densified by Spark Plasma Sintering for Accident-Tolerant Fuels, Ceramics International (December 2021) | Publication | FY2022 |
| Yarrington JD, Schulthess JL, Parker SH, Argyle JM, Turner CG, Stanek JD, Christensen CL. Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nucl Technol. 2022;209(2):127-143 | Publication | FY2022 |
| Zhang, B., Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System, in Proceedings of 2022 PHYSOR Conference, Pittsburgh, Pennsylvania, US. May 2022 | Publication | FY2022 |
| Balke T, Long AM, Vogel SC, Wohlberg B, Bouman CA. Hyperspectral neutron CT with material decomposition. 2021 IEEE International Conference on Image Processing (ICIP); 2021; Anchorage, AK, USA. pp. 3482-3486 | Publication | FY2021 |
| Beausoleil, G. L., Petrie, C., Williams, W., Jokisaari, A., Capriotti, L., Novascone, S., É Kerr, M. (2021). Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm. Nuclear Technology, 207(10), 1491 1510. | Publication | FY2021 |
| Bess, J.D., Pope, C.L., Chipman, A.S., & Jensen, C.B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization. Transactions of the American Nuclear Society, 124(1), 238-241. | Publication | FY2021 |
| Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions. Journal of Nuclear Materials, 546, 152750. | Publication | FY2021 |
| Chaari, N., Bischoff, J., Buchanan, K., Delafoy, C., Barberis, P., Augereau, J., & Nimishakavi, K. (2021). The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures. ASTM Symposia, 189-210. | Publication | FY2021 |
| Curnutt, R., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., Jensen, C., & Fradeneck, A. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623. | Publication | FY2021 |
| Duenas, A., Wachs, D., Mignot, G., Reyes, J. N., Wu, Q., & Marcum, W. (2021). Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering, 196(2), 193 208. | Publication | FY2021 |
| Gong, B., Cai, L., Lei, P., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2021 |
| Gong, B., Yao, T., Lei, P., Cai, L., Metzger, K.E., Lahoda, E.J., Boylan, F.A., Mohamad, A., Harp, J., Nelson, A.T., & Lian, J. (2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials, 534, 152147. | Publication | FY2021 |
| Gonzales, A., Watkins, J.K., Wagner, A.R., Jaques, B.J., & Sooby, E.S. (2021). Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide. Journal of Nuclear Materials, 553, 153026. | Publication | FY2021 |
| Gouws, A., Hagen, D., Chen, A., Kardoulaki, E., Beaman, J.J., & Kovar, D. Onset of selective laser flash sintering of AlN. United States. | Publication | FY2021 |
| Harp, J.M., Morris, R.N., Petrie, C.M., Burns, J.R., & Terrani, K.A. (2021). Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles. Journal of Nuclear Materials, 544, 152696. | Publication | FY2021 |
| Kardoulaki, E., Frazer, D.M., White, J.T., Carvajal, U., Nelson, A.T., Byler, D.D., Saleh, T.A., Gong, B., Yao, T., Lian, J., & McClellan, K.J. (2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials, 544, 152690. | Publication | FY2021 |
| Koyanagi, T., Wang, H., Arregui Mena, J.D., Petrie, C.M., Deck, C.P., Kim, W.-J., Kim, D., Sauder, C., Braun, J., & Katoh, Y. (2021). Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation. Journal of Nuclear Materials, 557, 153217. | Publication | FY2021 |
| Lee, D., Elward, B., Brooks, P., Umretiya, R., Rojas, J., Bucci, M., Rebak, R.B., & Anderson, M. (2021). Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Applied Thermal Engineering, 185, 116347. | Publication | FY2021 |
| Moorehead, M., Nelaturu, P., Elbakhshwan, M., Parkin, C., Zhang, C., Sridharan, K., Thoma, D.J., & Couet, A. (2021). High-throughput ion irradiation of additively manufactured compositionally complex alloys. Journal of Nuclear Materials, 547, 152782. | Publication | FY2021 |
| Mouche, P.A., Koyanagi, T., Patel, D., & Katoh, Y. (2021). Adhesion, structure, and mechanical properties of Cr HiPIMS and cathodic arc deposited coatings on SiC. Surface and Coatings Technology, 410, 126939. | Publication | FY2021 |
| Ingraci Neto, R.R., McClellan, K.J., Byler, D.D., & Kardoulaki, E. (2021). Controlled current-rate AC flash sintering of uranium dioxide. Journal of Nuclear Materials, 547, 152780. | Publication | FY2021 |
| Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., He, L., Sridharan, K., & Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85-99. | Publication | FY2021 |
| Petrie, C.M., Burns, J.R., Raftery, A.M., Nelson, A.T., & Terrani, K.A. (2019). Separate effects irradiation testing of miniature fuel specimens. Journal of Nuclear Materials, 526, 151783. | Publication | FY2021 |
| Radhakrishnan M, Kombaiah B, Bachhav MN, Nizolek TJ, Wang YQ, Knezevic M, Mara N, Anderoglu O. Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation. J Nucl Mater. 2021;557:153315, | Publication | FY2021 |
| Rietema, C.J., Hassan, M.M., Anderoglu, O., Eftink, B.P., Saleh, T.A., Maloy, S.A., Clarke, A.J., & Clarke, K.D. (2021). Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel. Scripta Materialia, 197, 113787. | Publication | FY2021 |
| Rietema, C.J., Walker, M.A., Jacobs, T.R., Clarke, A.J., & Clarke, K.D. (2021). High-throughput nitride and interstitial nitrogen analysis in ferritic/martensitic steels via time-of-flight secondary ion mass spectrometry. Materials Characterization, 179, 111357. | Publication | FY2021 |
| Roache, D.C., Bumgardner, C.H., Harrell, T.M., Price, M.C., Jarama, A., Heim, F.M., Walters, J., Maier, B., & Li, X. (2022). Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation. Surface and Coatings Technology, 429, 127909. | Publication | FY2021 |
| Wang, H., Gould, B., Moorehead, M., Haddad, M., Couet, A., & Wolff, S.J. (2022). In situ X-ray and thermal imaging of refractory high entropy alloying during laser directed deposition. Journal of Materials Processing Technology, 299, 117363. | Publication | FY2021 |
| Williams, W.J., Okuniewski, M.A., & Vogel, S.C. et al. (2020). In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing. JOM, 72, 2042 2050. | Publication | FY2021 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT. Nuclear Technology, 207(5), 637-652. | Publication | FY2021 |
| Xie, Y., Vogel, S.C., Harp, J.M., Benson, M.T., & Capriotti, L. (2021). Microstructure Evolution of U Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U 10Zr (wt. %). Journal of Nuclear Materials, 544, 152665. | Publication | FY2021 |
| Yang, J., Kardoulaki, E., Zhao, D., Broussard, A., Metzger, K., White, J.T., Sivack, M.R., McClellan, K.J., Lahoda, E.J., & Lian, J. (2021). Uranium nitride (UN) pellets with controllable microstructure and phase fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties. Journal of Nuclear Materials, 557, 153272. | Publication | FY2021 |
| Yin, L., Jurewicz, T.B., Larsen, M., Drobnjak, M., Graff, C.C., Lutz, D.R., & Rebak, R.B. (2021). Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors. Journal of Nuclear Materials, 554, 153090. | Publication | FY2021 |
| Agarwal, S. et al. Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy. Journal of Nuclear Materials 526 (2019): 151778 | Publication | FY2020 |
| Ali, A., Kim, H.-G., Hattar, K., Briggs, S., Park, D. J., Park, J. H., & Lee, Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. Nucl. Eng. Des. 362 (2020): 110581 | Publication | FY2020 |
| Baker, J. L., Wang, G., Ulrich, T. L., White, J. T., Batista, E. R., Yang, P., Roback, R. C., Park, C., & Xu, H. High-Pressure Structural Behavior and Elastic Properties of U3Si5: A Combined Synchrotron XRD and DFT Study. Journal of Nuclear Materials (2020) | Publication | FY2020 |
| Beausoleil GL, Petrie C, Williams W, Jokisaari A, Capriotti L, Novascone S, Kerr M. Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm. Nucl Technol. 2021;207(10):1491-1510 | Publication | FY2020 |
| Brown, N. R., Garrison, B. E., Lowden, R. R., Cinbiz, M. N., & Linton, K. D. Mechanical failure of fresh nuclear grade iron chromium aluminum (FeCrAl) cladding under simulated hot zero power reactivity-initiated accident conditions. Journal of Nuclear Materials (2020):152352 | Publication | FY2020 |
| Burns, J. R., Hernandez, R., Terrani, K. A., Nelson, A. T., & Brown, N. R. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%. Annals of Nuclear Energy, 142 (2020): 107423 | Publication | FY2020 |
| Bumgardner, C. H., Heim, F. M., Roache, D. C., Jarama, A., Xu, P., Lu, R., Lahoda, E. J., Croom, B. P., Deck, C. P., & Li, X. Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission. Journal of the American Ceramic Society (2019) | Publication | FY2020 |
| Capps, N., Sweet, R., Wirth, B. D., Nelson, A., Terrani, K. A. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient. Nuclear Engineering and Design 366 (2020): 110744, ISSN 0029-5493 | Publication | FY2020 |
| Capps, N., Yan, Y., Raftery, A., Burns, Z., Smith, T., Terrani, K. A., Yueh, K., Bales, M., & Linton, K. D. Integral LOCA fragmentation test on high-burnup fuel. Nuclear Eng. And Design 367 (2020): 110811 | Publication | FY2020 |
| Capriotti, L., & Harp, J. M. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II. Journal of Nuclear Materials 539 (2020): 152279 | Publication | FY2020 |
| Chichester, H. J. M., Hilton, B. A., Hayes, S. L., Capriotti, L., Medvedev, P. G., & Porter, D. L. (2020). Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels. Journal of Nuclear Materials, 542, 152480. | Publication | FY2020 |
| Cui, Y., Aydogan, E., Gigax, J. G., Wang, Y., Misra, A., Maloy, S. A., Li, N. (2021). In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys. Acta Materialia, 202, 255-265. | Publication | FY2020 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. Experimental Evaluation of Cold Spray FeCrAl Alloys Coated Zirconium-alloy for Potential Accident Tolerant Fuel Cladding. Nuclear Materials and Energy 21 (2019): 100715 | Publication | FY2020 |
| Deng, P., Karadge, M., Rebak, R. B., Gupta, V. K., Prorok, B. C., & Lou, X. The origin and formation of oxygen inclusions in austenitic stainless steels manufactured by laser powder fusion. Additive Manufacturing 35 (2020):101334 | Publication | FY2020 |
| Doyle, P. J. et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials (2020): 152203 | Publication | FY2020 |
| Doyle, P. J. et al. The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC. Journal of Nuclear Materials (2020):152190 | Publication | FY2020 |
| Doyle, P. J., Zinkle, S., & Raiman, S. S. Hydrothermal corrosion behavior of CVD SiC in high temperature water. Journal of Nuclear Materials (2020):152241 | Publication | FY2020 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., Xu, C., Hoelzer, D. T., Saleh, T. A., & Maloy, S. A. Shear Punch Testing of Neutron-Irradiated HT-9 and 14YWT. JOM 72 (2020) | Publication | FY2020 |
| Evitts, L. J., Middleburgh, S. C., Kardoulaki, E., Ipatova, I., Rushton, M. J. D., & Lee, W. E. Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2). Journal of Nuclear Materials (2020):1 7. | Publication | FY2020 |
| Gigax, J., Torrez, A., McCulloch, Q., Kim, H., Li, N., & Maloy, S. Sizing up mechanical testing: Comparison of microscale and mesoscale mechanical testing techniques on a FeCrAl welded tube. J. Mater. Res. (2020) | Publication | FY2020 |
| Gong, B., Yao, T., Lei, P., Lu, C., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Mohamad, A., Harp, J., Nelson, A. T., & Lian, J. U3Si2 and UO2 composites densified by spark plasma sintering for accident tolerant fuels. Journal of Nuclear Materials 534 (2020): 152147 | Publication | FY2020 |
| Gong, B., Cai, L., Lei, P., Metzger, K. E., Lahoda, E. J., Boylan, F. A., Yang, K., Fay, J., Harp, J., & Lian, J. (2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science, 177, 109001. | Publication | FY2020 |
| Gorton, J. P., Lee, S. K., Lee, Y., & Brown, N. R. Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nucl. Eng. Des. 353 (2019): 110295 | Publication | FY2020 |
| Harp, J. M., Capriotti, L., Porter, D. L., & Cole, J. I. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences. Journal of Nuclear Materials 528 (2020): 151840 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: Support vector machine for data-driven CHF look-up table construction based on sparingly distributed training data points. Nucl. Eng. Des. 338 (2018):189 198 | Publication | FY2020 |
| He, M., & Lee, Y. Application of Deep Belief Network for Critical Heat Flux Prediction on Microstructure Surfaces. Nuclear Technology 206 (2020):358 374 | Publication | FY2020 |
| He, M., & Lee, Y. Application of machine learning for prediction of critical heat flux: He, M., & Lee, Y. Revisiting heater size sensitive pool boiling critical heat flux using neural network modeling: Heater length of the half of the Rayleigh-Taylor Instability Wavelength maximizes CHF. Therm. Sci. Eng. Prog. 14 (2019): 100421 | Publication | FY2020 |
| Heim, F. M., Daspit, J. T., Holzmond, O. B., Croom, B. P., & Li, X. Analysis of tow architecture variability in biaxially braided composite tubes. Composites Part B: Engineering 190 (2020): 107938 | Publication | FY2020 |
| Heim FM, Daspit JT, Li X. Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes. Compos Part B Eng. 2020;201:108383 | Publication | FY2020 |
| Johnson, K. E., Adorno, D. L., Kocevski, V., Ulrich, T. L., White, J. T., Claisse, A., McMurrary, J. W., & Besmann, T. M. Impact of Fission Product Inclusion on Phase Development in U3Si2 Fuel. Journal of Nuclear Materials 537 (2020): 152235 | Publication | FY2020 |
| Jo, H., Yeom, H., Gutierrez, E., Sridharan, K., & Corradini, M. Evaluation of Critical Heat Flux of ATF Candidate Coating Materials in Pool Boiling. Nuclear Engineering and Design 354 (2019): 110166 | Publication | FY2020 |
| Kane, K. A., Lee, S. K., Bell, S. B., Brown, N. R., & Pint, B. A. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions. Journal of Nuclear Materials 539 (2020): 152256 | Publication | FY2020 |
| Kardoulaki, E., White, J. T., Byler, D. D., Frazer, D. M., Shivprasad, A. P., Saleh, T. A., Gong, B., Yao, T., Lian, J., & McClellan, K. J. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. J. Alloys Compd. 818 (2020): 1 14. | Publication | FY2020 |
| Kocevski, V., Lopes, D. A., Claisse, A. J., & Besmann, T. M. Understanding the interface interaction between U3Si2 fuel and SiC cladding. Nature Communications 11 (1) (2020): 1-8 | Publication | FY2020 |
| Koyanagi, T., Katoh, Y., & Nozawa, T. Design and strategy for next-generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials (2020):152375 | Publication | FY2020 |
| Le Coq, A. G., Morris, R. N., Petrie, C. M., & Burns, J. R. Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor. Transactions of the American Nuclear Society 121 (2019):615-618 | Publication | FY2020 |
| Lee D, Elward B, Brooks P, et al. Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials. Appl Therm Eng. 2021;185:116347 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., Blandford, E. D., Ban, H., Jensen, C. B., & Lee, Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel. Int. J. Heat Mass Transf. 132 (2019): 643 654 | Publication | FY2020 |
| Lee, S. K., Liu, M., Brown, N. R., Terrani, K. A., & Lee, Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux. Nuclear Technology 206 (2020): 339 346 | Publication | FY2020 |
| Lee, S. K., Lee, Y., Brown, N. R., & Terrani, K. A. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials. International J. Heat Mass Transf. 158 (2020): 119970 | Publication | FY2020 |
| Losko, A. S., Daemen, L., Hosemann, P., Nakotte, H., Tremsin, A., Vogel, S. C., Wang, P., & Wittman, F. H. Separation of Uptake of Water and Ions in Porous Materials Using Energy Resolved Neutron Imaging. JOM (2020): 1-8 | Publication | FY2020 |
| McCulloch, Q., Gigax, J., & Hosemann, P. Femtosecond laser ablation for mesoscale specimen evaluation. JOM 72(4) (2020): 1694 | Publication | FY2020 |
| McKinney, C., Gerczak, T. J., & Harp, J. Sample Preparation for 3D Characterization of Irradiated Fuel. United States: N. p., 2020. Web. | Publication | FY2020 |
| Mouche, P. A. et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials 527 (2019): 151781 | Publication | FY2020 |
| Mouche, P. A., & Terrani, K. A. Steam pressure and velocity effects on high temperature silicon carbide oxidation. Journal of the American Ceramic Society 103.3 (2020): 2062-2075 | Publication | FY2020 |
| Peterson, N. E., Malta, D., Vogel, S. C., Clausen, B., Jana, S., Joshi, V. V., & Agnew, S. R. The role of ternary alloying elements in eutectoid transformation of U 10Mo alloy part II. In and ex-situ neutron diffraction-based assessment of eutectoid phase transformation kinetics in U-9.8 Mo-0.2 X alloy (X= Cr, Ni or Co). Journal of Nuclear Materials 540 (2020):152383 | Publication | FY2020 |
| Petrie, C. M., Le Coq, A., Richardson, D., Hobbs, C., Helmreich, G., Burns, J., & Harp, J. Monolithic ATF MiniFuel Sample Capsules Ready for HFIR Insertion. United States: N. p., 2020. Web. | Publication | FY2020 |
| Raiman, S. S., Field, K. G., Rebak, R. B., Yamamoto, Y., & Terrani, K. A. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding. Journal of Nuclear Materials 536. | Publication | FY2020 |
| Rebak, R. B., Yin, L., & Andresen, P. L. Resistance of ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications. Corrosion Journal, NACE International | Publication | FY2020 |
| Reed, B., Wang, R., Lu, R. Y., & Qu, J. (2021). Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel. Wear, 466-467, 203578 | Publication | FY2020 |
| Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT. Journal of Nuclear Materials 541 (2020): 152442 | Publication | FY2020 |
| Su, G. Y., Wang, C., Zhang, L., Seong, J. H., Phillips, B., Kommayosula, R., & Bucci, M. Investigation of flow boiling heat transfer and boiling crisis on a rough surface using infrared thermometry. International Journal of Heat and Mass Transfer 160 (2020): 120134 | Publication | FY2020 |
| Terrani, K. A., Jolly, B. C., & Harp, J. M. Uranium nitride tristructural-isotropic fuel particle. Journal of Nuclear Materials 531 (2020): 152034 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., Lopes, D. A., Kocevski, V., White, J. T., Sooby, E. S., & Besmann, T. M. Phase stability of U5Si4, Usi, and U2Si3 in the uranium silicon system. Journal of Nuclear Materials 540 (2020): 152353 | Publication | FY2020 |
| Ulrich, T. L., Vogel, S. C., White, J. T., Andersson, D. A., Wood, E. S., & Besmann, T. M. High temperature neutron diffraction investigation of U3Si2. Materialia 9 (2020):100580 | Publication | FY2020 |
| Umretiya, R. V., Elward, B., Lee, D., Anderson, M., Rebak, R. B., & Rojas, J. V. Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4. Journal of Nuclear Materials 541 (2020): 152420 | Publication | FY2020 |
| Umretiya, R. V., Vargas, S., Galeano, D., Mohammadi, R., Castano, C. E., & Rojas, J. V. Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material. Journal of Nuclear Materials (2020): 152163 | Publication | FY2020 |
| Vogel, S. C., Fernandez, J. C., Gautier, D. C., Mitura, N., Roth, M., & Schoenberg, K. F. Short-Pulse Laser-Driven Moderated Neutron Source. EPJ Web of Conferences 231 (2020): 01008). EDP Sciences | Publication | FY2020 |
| Vogel, S. C., Bourke, M. A., Craft, A. E., Harp, J. M., Kelsey, C. T., Lin, J., Long, A. M., Losko, A. S., Hosemann, P., McClellan, K. J., & Roth, M. Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons. JOM 72(1) (2020): 187-196 | Publication | FY2020 |
| Williams, W. J., Okuniewski, M. A., Vogel, S. C., & Zhang, J. In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.% Zr During Annealing. JOM (2020): 1-9 | Publication | FY2020 |
| Sooby Wood, E., Moczygemba, C., Robles, G., Acosta, Z., Brigham, B. A., Grote, C. J., Metzger, K. E., & Cai, L. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y. Journal of Nuclear Materials 533 (2020) | Publication | FY2020 |
| Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy (2020) | Publication | FY2020 |
| Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2020). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652 | Publication | FY2020 |
| Yao, T., Gong, B., Lei, P., Lu, C., Xu, P., Lahoda, E., & Lian, J. (2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International, 46(17), 26486-26491 | Publication | FY2020 |
| Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. Nucl Eng Des. 2020;370:110919 | Publication | FY2020 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., Sevecek, M. & J. Schulthess. Development of Axial and Ring Hoop Tension Testing Methods for Nuclear Fuel Cladding Tubes, Nuclear Materials and Energy, Volume 31 (2022) | Publication | FY2022 |
| U.S. Department of Energy. (2023). Alternate fuels: Thorium and Uranium-233. Thorium Energy Alliance. | Publication | FY2023 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., & White, J. T. (2019). Processing and characterization of U3Si2 at the MiniFuel scale (Report No. LA-UR-19-26376). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Abdul-Jabbar, N. M., Grote, C. J., & White, J. T. (2019). Assessment of thermophysical property characterization of MiniFuel scale geometries (Report No. LA-UR-19-24287). Los Alamos National Laboratory. | Publication | 2019 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Fields, K., Maloy, S. A., Hoelzer, D. T., & Odette, G. R. (2016). Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy. Materials Science and Engineering: A, 675, 437-448. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alam, M. E., Pal, S., Maloy, S. A., & Odette, G. R. (2017). On delamination toughening of a 14YWT nanostructured ferritic alloy. Acta Materialia, 136, 61-73. | Publication | 2017 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Alat, E., Motta, A. T., Comstock, R. J., Partezana, J. M., & Wolfe, D. E. (2015). Ceramic coating for corrosion (C3) resistance of nuclear fuel cladding. Surface and Coatings Technology, 281, 133-143. | Publication | 2016 |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Aliberity, G., Kim, T. K., & Stauff, N. (2017). Assessment of AmBB performance and tradeoff of advanced fuel concepts (FY 2017, NTRD-FUEL-2017-00012). September 30, 2017. | 2017 | |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Alva, L., Shapovalov, K., Jacobsen, G. M., Back, C. A., & Huang, X. (2015). Experimental study of thermo-mechanical behavior of SiC composite tubing under high temperature gradient using solid surrogate. Journal of Nuclear Materials, 466, 698-711. | Publication | 2016 |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O. (2016). In situ synchrotron characterization of the field assisted sintering of UO2. In ANS 2016 - Poster presentation and extended abstract. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., & Saleh, T. A. (2016). Microstructural investigation of ATR irradiated (290°C to 6 dpa) MA956. Submitted for milestone Microstructural, Analysis of ATR Irradiated FeCrAl ODS alloys, M3FT-16LA020202082. | 2016 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | 2013 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | 2012 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C. K., Kiggans, J., Kemery, C., O'Dell, S., Burns, J., Terrani, K. A., & Katoh, Y. (2016). Mechanical properties and characterization of coated SiC fuel cladding. Transactions of American Nuclear Society, 115(1), 433-435. | Publication | 2017 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Carpenter, D., Terrani, K., & Katoh, Y. (2018, November). Preliminary characterization and projections of PVD coatings on SiC cladding for light water reactors. In Proceedings of the 42nd International Conference on Advanced Ceramics and Composites, Ceramic Engineering and Science Proceedings 3, 119. John Wiley & Sons. | Publication | 2019 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Katoh, Y., Kemery, C., Kiggans, J., & Terrani, K. (2016). Chromium-based mitigation coatings on SiC materials for fuel cladding. Transactions of American Nuclear Society, 114(1), 1095-1097. | Publication | 2017 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Kemery, C., & Katoh, Y. (2018). Electroplating chromium on CVD SiC and SiCf-SiC advanced cladding via PyC compatibility coating. Journal of Nuclear Materials, 503, 245-249. | Publication | 2019 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Raiman, S., Burns, J., Hu, X., & Katoh, Y. (2017). Evaluation of the first generation dual-purpose coatings for SiC cladding (ORNL/SR-2017/318). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Ang, C., Terrani, K., Burns, J., & Katoh, Y. (2016). Examination of hybrid metal coatings for mitigation of fission product release and corrosion protection of LWR SiC/SiC (ORNL/TM-2016/332). Oak Ridge National Laboratory, Oak Ridge, TN. | Publication | 2017 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Angle, J. P., Nelson, A. T., Men, D., & Mecartney, M. L. (2014). Thermal measurements and computational simulations of three-phase (CeO2MgAl2O4CeMgAl11O19) and four-phase (3Y-TZPAl2O3MgAl2O4LaPO4) composites as surrogate inert matrix nuclear fuel. Journal of Nuclear Materials, 454(1-3), 69-76. | Publication | 2015 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Antonio, D. J., Shrestha, K., Harp, J. M., Adkins, C. A., Zhang, Y., Carmack, J., & Gofryk, K. (2018). Thermal and transport properties of U3Si2. Journal of Nuclear Materials, 508, 154-158. | Publication | 2017 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Arndt, J. L., Lahoda, E. J., & Oelrich, R. L. (2018, June 3-6). Westinghouse accident tolerant fuel and its benefits for CANDU reactors. In Proceedings of the 38th Annual Conference of the Canadian Nuclear Society, Saskatoon, SK, Canada. | Publication | 2018 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., Almirall, N., Odette, G. R., Maloy, S. A., Anderoglu, O., Shao, L., Gigax, J. G., Price, L., Chen, D., Chen, T., Garner, F. A., Wu, Y., Wells, P., Lewandowski, J. J., & Hoelzer, D. T. (2017). Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. Journal of Nuclear Materials, 486, 86-95. | Publication | 2017 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., El-Atwani, O., Takajo, S., Vogel, S. C., & Maloy, S. A. (2018). High temperature microstructural stability and recrystallization mechanisms in 14YWT alloys. Acta Materialia, 148, 467-481. | Publication | 2018 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Maloy, S. A., Anderoglu, O., Sun, C., Gigax, J. G., Shao, L., Garner, F. A., Anderson, I. E., & Lewandowski, J. J. (2017). Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys. Acta Materialia, 134, 116-127. | Publication | 2017 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Pal, S., Anderoglu, O., Maloy, S. A., Vogel, S. C., Odette, G. R., Lewandowski, J. J., Hoelzer, D. T., Anderson, I. E., & Rieken, J. R. (2016). Effect of tube processing methods on the texture and grain boundary characteristics of 14YWT nanostructured ferritic alloys. Materials Science and Engineering: A, 661, 222-232. | Publication | 2016 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Rietema, C. J., Carvajal-Nunez, U., Vogel, S. C., Li, M., & Maloy, S. A. (2019). Effect of high-density nanoparticles on recrystallization and texture evolution in ferritic alloys. Crystals, 9(3), 172. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Aydogan, E., Weaver, J. S., Carvajal-Nunez, U., Schneider, M. M., Gigax, J. G., Krumwiede, D. L., Hosemann, P., Saleh, T. A., Mara, N. A., Hoelzer, D. T., Hilton, B., & Maloy, S. A. (2019). Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties. Acta Materialia, 167, 181-196. | Publication | 2019 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Bacalski, C. F., Jacobsen, G. M., & Deck, C. P. (Sept. 12-14, 2016). Characterization of SiC-SiC accident tolerant fuel cladding after stress application. In American Nuclear Society TOP FUEL 2016 Proceedings (pp. 843-848). Boise, Idaho. | Publication | 2016 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Baek, J.-H., Byun, T. S., Maloy, S. A., & Toloczko, M. B. (2014). Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique. Journal of Nuclear Materials, 444(13), 206-213. | Publication | 2014 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | 2015 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Baker, K. E., Ellis, K., & Glass, C. (April 2016). BISON fuel performance code examination of coating/clad interfaces for accident tolerant fuels irradiation testing. In TMS 2016 Meeting Conference Proceedings. | 2016 | |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | 2015 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Durtschi, B. P., Daw, J., Unruh, T., Smith, J., Woolum, C. T., Davis, K. L., & Chichester, H. J. M. (2016). Sensor qualification tests in preparation for accident tolerant fuels water loop irradiation testing in the Advanced Test Reactor at the INL. In Enhanced Halden Reactor Project Meeting, Oslo, Norway, May 9-12, 2016. | Publication | 2016 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | 2015 |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beasley, A., Hill, C., Housley, G., Jensen, C., OBrien, R., & Woolstenhulme, N. (2015). TREAT water loop status report (INL/LTD-15-36768). Idaho National Laboratory. | 2015 | |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G. L., Povirk, G. L., & Curnutt, B. J. (2020). A revised capsule design for the accelerated testing of advanced reactor fuels. Nuclear Technology, 206(3), 444-457. | Publication | 2019 |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beausoleil, G., Cappia, F., Emerson, L. A., Murray, D., Sell, D., Christensen, C., Winston, A., Wahlquist, D., Bachhav, M., & Miller, B. (2019). Separate effects testing in TREAT for ATF fuels. Portions of this work were presented in a poster session at The Mineral, Metals, and Materials Society (TMS) 2019 annual meeting in San Antonio, TX. | 2019 | |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2010). First principles calculations for defects in U. Journal of Physics: Condensed Matter, 22(50), 505703. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Beeler, B., Good, B., Rashkeev, S., Deo, C., Baskes, M., & Okuniewski, M. (2012). First-principles calculations of the stability and incorporation of helium, xenon and krypton in uranium. Journal of Nuclear Materials, 425(13), 2-7. | Publication | 2011 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | 2012 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | 2011 | |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive. Journal of Nuclear Materials, 502, 106-112. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., He, L., King, J. A., Mariani, R. D., Winston, A. J., & Madden, J. W. (2018). Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 508, 310-318. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., & Mariani, R. D. (2018). Investigation of tin as a fuel additive to control FCCI. In TMS 2018 147th Annual Meeting & Exhibition Supplemental Proceedings (pp. 695-702). The Minerals, Metals & Materials Series. Springer, Cham. | Publication | 2018 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., King, J. A., Mariani, R. D., & Marshall, M. C. (2017). SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln. Journal of Nuclear Materials, 494, 334-341. | Publication | 2017 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., Mariani, R. D., Hernandez, B. J., Murray, D. J., & Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287-297. | Publication | 2019 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Benson, M. T., Xie, Y., King, J. A., Tolman, K. R., Mariani, R. D., Charit, I., Zhang, J., Short, M. P., Choudhury, S., Khanal, R., & Jerred, N. (2018). Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides. Journal of Nuclear Materials, 510, 210-218. | Publication | 2018 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Bentzel, G. W., Naguib, M., Lane, N. J., Vogel, S. C., Presser, V., Dubois, S., Lu, J., Hultman, L., Barsoum, M. W., & Caspi, E. N. (2016). High-temperature neutron diffraction, Raman spectroscopy, and first-principles calculations of Ti3SnC2 and Ti2SnC. Journal of the American Ceramic Society, 99(7), 2233-2242. | Publication | 2016 |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. (2014). Fiscal year 2014 summary report on thermodynamic assessment of advanced accident tolerant fuel compositions (Milestone No. M3FT-14OR02021810). | 2016 | |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | 2014 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Besmann, T. M., Noorhoek, M. J., Wilson, T., Nelson, A. T., Wood, E. S., McMurray, J. W., Shin, D., Lahoda, E. J., & Middleburgh, S. C. (2017). Uranium silicide-nitride fuels: Thermochemical behavior and compatibility. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Hill, C. M., Woolstenhulme, N. E., & Jensen, C. B. (2017). Analyses supporting design review of TREAT multi-SERTTA experiment test vehicle. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, Republic of, April 16-20, 2017. | Publication | 2017 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., & Snow, S. D. (2016). TREAT neutronics analysis and design support, part I: Multi-SERTTA. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., OBrien, R. C., & Bays, S. E. (2016). TREAT Multi-SERTTA neutronics design and analysis support. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D., & Jensen, C. B. (2016). TREAT neutronics analysis and design support, part II: Multi-SERTTA-CAL. In Proceedings of the Top Fuel 2016 Conference, Boise, Idaho, USA, Sep 11-16, 2016. | Publication | 2016 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294. | Publication | 2019 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Betzler, B. R., & Powers, J. J. (2016). A fully ceramic microencapsulated fuel for space reactor applications. In Proceedings of PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 2016. | Publication | 2016 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bhattacharyya, D., Dickerson, P., Odette, G. R., Maloy, S. A., Misra, A., & Nastasi, M. A. (2012). On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT. Philosophical Magazine, 92(16), 20892107. | Publication | 2013 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Delafoy, C., Vauglin, C., Barberis, P., Roubeyrie, C., Perche, D., Duthoo, D., Schuster, F., Brachet, J.-C., Schweitzer, E. W., & Nimishakavi, K. (2018). AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding. Nuclear Engineering and Technology, 50(2), 223-228. | Publication | 2018 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bischoff, J., Vauglin, C., Delafoy, C., Barberis, P., Perche, D., Guerin, B., Vassault, J. P., & Brachet, J. C. (2016). Development of Cr-coated zirconium alloy cladding for enhanced accident tolerance. In ANS Top Fuel 2016 Meeting Proceedings (pp. 1165-1171), Boise, ID, September 11-15, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | 2014 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | FY2010 |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | 2014 | |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| Bragg-Sitton, S. M., & Carmack, W. J. (2014). Advanced Fuels Campaign: Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957, FCRD-FUEL-2013-000264). February 2014. | Publication | 2016 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | FY2010 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Bragg-Sitton, S. M., Todosow, M., Montgomery, R., Stanek, C. R., & Carmack, W. J. (2016). Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel. Nuclear Technology, 195(2), 111-123. | Publication | 2016 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | FY2010 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | 2014 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | FY2010 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Brese, R. G., McMurray, J. W., Shin, D., & Besmann, T. M. (2015). Thermodynamic assessment of the UYO system. Journal of Nuclear Materials, 460, 5-12. | Publication | 2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | FY2010 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | 2014 |
| Mariani, R. (2010). Dopants for high burnup in metallic nuclear fuels. U.S. Patent No. 12/702,077. Filed February 8, 2010. | FY2010 | |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | 2015 |
| Mariani, R. (2010). Nuclear fuel bodies having shell and core regions, nuclear reactors including such nuclear fuel bodies, and related methods. U.S. Patent No. 12/893,503. Filed September 29, 2010. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | 2013 |
| Mohammadian, M. A., Allen, T. R., Sridharan, K., Cole, J. I., Fielding, R. F., & Young, C. (n.d.). Characterization of vanadium-lined fuel cladding fabricated with various process parameters. Manuscript submitted for publication, Journal of Nuclear Materials. | FY2010 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | 2013 |
| Nerikar, P. V., Rudman, K., Desai, T. G., Byler, D., Unal, C., McClellan, K. J., Phillpot, S. R., Sinnott, S. B., Peralta, P., Uberuaga, B. P., & Stanek, C. R. (2010). Grain boundaries in uranium dioxide: Scanning electron microscopy experiments and atomistic simulations. Journal of the American Ceramic Society, 94(6), 1893-1900. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Brown, N. R., Todosow, M., & Cuadra, A. (2015). Screening of advanced cladding materials and UNU3Si5 fuel. Journal of Nuclear Materials, 462, 26-42. | Publication | 2015 |
| Park, S. K., Baik, S. H., Cha, H. K., Reese, S. J., & Hurley, D. H. (2010). Characteristics of laser resonant ultrasonic spectroscopy system for measuring elastic constants of materials. Journal of the Korean Physical Society, 57, 375-379. | Publication | FY2010 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Kyoto, Japan, September 28 October 3, 2014. | Publication | 2014 |
| Rudman, K., Peralta, P., Stanek, C., Wheeler, K., Parra, M., Byler, D., & McClellan, K. (2010). Quantification of microstructure variability in surrogates for oxide nuclear fuels. In TMS Annual Meeting, Seattle, WA. | FY2010 | |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., & McClellan, K. J. (2014). Uranium nitride composite fuels in a pressurized water reactor: Exploration of multi-batch cycle length and UB4 admixture for reactivity control. In Proceedings of PHYSOR 2014 The Role of Reactor Physics Toward a Sustainable Future. Miyako, Kyoto, Japan. | Publication | 2014 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | 2015 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., & Terrani, K. A. (2016). Reactivity initiated accident simulation to inform transient testing of candidate advanced cladding. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 271-285). American Nuclear Society. Boise, ID, September 11-16, 2016. | Publication | 2016 |
| Bell, G. L., McDuffee, J., Hobbs, R. W., Ott, L. J., Ellis, R. J., Okuniewski, M. A., & Hayes, S. L. (2010, November). Preparations for low fluence fuels testing in the High Flux Isotope Reactor hydraulic rabbit facility. In OECD Nuclear Energy Agency Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, CA. | FY2011 | |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Ali, A., Liu, M., & Blandford, E. (June 2016). Survey of thermal-fluids evaluation and confirmatory experimental validation requirements of accident tolerant cladding concepts with focus on boiling heat transfer characteristics (FCRD Milestone M3FT-16OR020204032, ORNL/TM-2016-252). | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Brown, N. R., Wysocki, A. J., Terrani, K. A., Xu, K. G., & Wachs, D. M. (2017). The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors. Annals of Nuclear Energy, 99, 353-365. | Publication | 2016 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | FY2011 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burns, J. R., Petrie, C. M., & Chandler, D. (2019). Burnup calculation methodology for a small-scale fuel irradiation experiment in the High Flux Isotope Reactor (HFIR). Transactions of the American Nuclear Society, 120, 841-844. | Publication | 2019 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Burr, P. A., Horlait, D., & Lee, W. E. (2016). Experimental and DFT investigation of (Cr,Ti)3AlC2 MAX phases stability. Materials Research Letters, 5(3), 144-157. | Publication | 2017 |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Byler, D., & Valdez, J. (2014). Report on synthesis of high-density ceramic composite materials with microstructural and chemical characterization (LA-UR-14-24678). | 2016 | |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | FY2011 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Byun, T. S., Baek, J.-H., Anderoglu, O., Maloy, S. A., & Toloczko, M. B. (2014). Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses. Journal of Nuclear Materials, 449(13), 263-272. | Publication | 2014 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | FY2011 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Byun, T. S., Toloczko, M. B., Saleh, T. A., & Maloy, S. A. (2013). Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF. Journal of Nuclear Materials, 432(13), 1-8. | Publication | 2013 |
| Mariani, R. D. (2011). Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys and related methods (U.S. Patent Application No. 13/021,480). U.S. Patent and Trademark Office. | FY2011 | |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Hoelzer, D. T., Lee, Y. B., Kang, S. H., & Maloy, S. A. (2014). Process development for 9Cr nanostructured ferritic alloy (NFA) with high fracture toughness. Journal of Nuclear Materials, 449(13), 290-299. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Byun, T. S., Yoon, J. H., Wee, S. H., Hoelzer, D. T., & Maloy, S. A. (2014). Fracture behavior of 9Cr nanostructured ferritic alloy with improved fracture toughness. Journal of Nuclear Materials, 449(13), 39-48. | Publication | 2014 |
| Myers, M. T., Sencer, B. H., & Shao, L. (2012). Multi-scale modeling of localized heating caused by ion bombardment. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 272, 165-168. | Publication | FY2011 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Cai, L., Xu, P., Atwood, A., Boylan, F., & Lahoda, E. J. (2017). Thermal analysis of ATF fuel materials at Westinghouse. In Proceedings of the International Conference and Exposition on Advanced Ceramics and Composites (ICACC), Daytona Beach, FL, January, 2017. | Publication | 2017 |
| Rempe, J. L., Knudson, D. L., Daw, J. E., Palmer, J. R., Condie, K. G., & Skerjanc, W. F. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Capps, N., Mai, A., Kennard, M., & Liu, W. (2018). PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code. Nuclear Engineering and Design, 332, 383-391. | Publication | 2018 |
| Rempe, J., Knudson, D. L., Daw, J., Condie, K. G., Palmer, J. R., Skerjanc, W. F., Wilkins, S. C., & Davis, K. L. (2012). Enhanced in-pile instrumentation at the Advanced Test Reactor. IEEE Transactions on Nuclear Science, 59(4), 1214-1223. | Publication | FY2011 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | 2014 | |
| Xing, C., Hua, Z., Ban, H., Hurley, D., & Kennedy, J. R. (2011). Evaluation of uncertainties of one-directional analytical model for thermoreflectance technique. Proceedings of the ASME 2011 International Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Microsystems, AJTEC2011-44539, T10057. | Publication | FY2011 |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Carmack, J. (2015). Enhanced accident tolerant fuels for LWRs technical review committee charter (FCRD-FUEL-2015-000021). March 2015. | 2016 | |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. In Proceedings of the ASME 2010 International Mechanical Engineering Congress and Exposition, Volume 7: Fluid Flow, Heat Transfer and Thermal Systems, Parts A and B (pp. 403-408). Vancouver, British Columbia, Canada. American Society of Mechanical Engineers. ASME. | Publication | FY2011 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | 2012 |
| Xing, C., Jensen, C., Ban, H., Mariani, R., & Kennedy, J. R. (2010). An electromotive force measurement system for alloy fuels. Proceedings of the ASME 2010 International Mechanical Engineering Congress & Exposition, Paper No: IMECE2010-39457, 403-408. | Publication | FY2011 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Carvajal-Nunez, U., et al. (2018). Mechanical properties of uranium silicides by nanoindentation and finite elements modeling. The Journal of The Minerals, Metals, & Materials Society, 70, 203-208. | Publication | 2018 |
| Anderoglu, O., Van den Bosch, J., Hosemann, P., Stergar, E., Sencer, B. H., Bhattacharyya, D., Dickerson, R., Dickerson, P., Hartl, M., & Maloy, S. A. (2012). Phase stability of an HT-9 duct irradiated in FFTF. Journal of Nuclear Materials, 430(1-3), 194-204. | Publication | FY2012 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | Publication | 2017 |
| Bell, G. L., McDuffee, J. L., Ellis, R. J., Glasgow, D. C., Sitterson, R. G., Snead, L. L., & Schmidlin, J. E. (2012). Summary of FY12 HFIR irradiation testing activities (ORNL/TM-2012/454). Oak Ridge National Laboratory. | FY2012 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carvajal-Nunez, U., Saleh, T. A., White, J. T., Maiorov, B., & Nelson, A. T. (2018). Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy. Journal of Nuclear Materials, 498, 438-444. | 2018 | |
| Carmack, W. J., Porter, D. L., Chichester, H. J., & Hayes, S. L. (2012, September 24-27). Irradiation performance comparison of experimental and prototypic length metallic (U-10Zr) fuel. In 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic. | Publication | FY2012 |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Carvajal-Nunez, U., White, J. T., Wood, E. S., Mara, N. A., & Nelson, A. T. (2016). Nanoscale mechanical behavior of uranium silicide compounds. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 1435-1441). | 2017 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chao-Chen Wei, Assel Aitkaliyeva, Zhiping Luo, Ashley Ewh, Y.H. Sohn, J.R. Kennedy, | 2012 | |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Che, Y., Pastore, G., Hales, J., & Shirvan, K. (2018). Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. Nuclear Engineering and Design, 337, 271-278. | Publication | 2018 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 Â The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | FY2012 |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Cheng, B., Chou, P., Topbasi, C., Kim, Y., Armijo, S., Do, C., & Ring, P. (2016). Fabrication of rodlets with coated and lined Mo-alloy cladding for testing and irradiation. In ANS Top Fuel 2016 Meeting Proceedings (pp. 207-216), Boise, ID, September 11-15, 2016. | 2016 | |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | FY2012 |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Chichester, H. J. M., Core, G. M., Barrett, K. E., & Wachs, D. M. (2016). Irradiation testing strategy for U.S. accident tolerant fuels. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | FY2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Chichester, H. J. M., Mariani, R. D., Hayes, S. L., Kennedy, J. R., Wright, A. E., Kim, Y. S., Yacout, A. M., & Hofman, G. L. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions, 106(1), 1349-1351. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session. Chicago, IL, 24-28 June 2012. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | FY2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Chichester, H. J. M., Porter, D. L., & Hayes, S. L. (2012, September 24-27). Postirradiation examination of high burnup metallic fuels for transmutation. In HOTLAB 2012 The 49th Conference on Hot Laboratories and Remote Handling, Marcoule, France. 24-27 September 2012. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | FY2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Chichester, H., Mariani, R., Hayes, S. L., Kennedy, J. R., Wright, A., Kim, Y. S., Yacout, A., & Hofman, G. (2012). Advanced metallic fuel for ultra-high burnup: Irradiation tests in ATR. Transactions of the American Nuclear Society, 106, 1349-1351. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | FY2012 |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Chipaux, R., Cecilia, G., Beauvy, M., & Troc, R. (1986). Capacite thermique a haute temperature de UBe13, ThBe13 et UB4. Journal of Less-Common Metals, 121, 347-351. | 2018 | |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| Choi, K., Tong, W., Maiani, R. D., Burkes, D. E., & Munir, Z. A. (2010). Densification of nano-CeO2 ceramics as nuclear oxide surrogate by spark plasma sintering. Journal of Nuclear Materials, 404(3), 210-216. | Publication | 2010 |
| McDonald, R., Rudman, K., Luther, E., Peralta, P., Stanek, C., & McClellan, K. (2012). Porosity characterization of surrogates for oxide nuclear fuels: A statistical analysis of correlations among grain boundary misorientation and pore character and location. Poster presentation at the TMS Annual Meeting, Orlando, FL. 2012. Poster presentation. | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Erdman, D., & Terrani, K. A. (2016). Issue report documenting simulated PCI testing (FCRD Milestone M3FT-16OR020204031). September 9, 2016. | 2016 | |
| Pint, B. A., Brady, M. P., Keiser, J. R., Cheng, T., & Terrani, K. A. (2012, May). High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. In Proceedings of the 8th International Symposium on High Temperature Corrosion and Protection of Materials, Les Embiez, France (Paper #89). | FY2012 | |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Cinbiz, M. N., Brown, N. R., Lowden, R. R., Gussev, M., Linton, K., & Terrani, K. A. (2018). Report on design and failure limits of SiC/SiC and FeCrAl ATF cladding concepts under RIA (ORNL/LTR-2018/521 NT-M3FT-2018-204032). Oak Ridge National Laboratory. | Publication | 2018 |
| Teague, M. M. (2012). Post irradiation examination of legacy FFTF oxide fuel (INL/LTD-1226386). | FY2012 | |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Cinbiz, N., Brown, N., Terrani, K. A., Lowden, R. R., & Erdman, D. (2017). The mechanical response evaluation of advanced claddings during proposed reactivity initiated accident conditions. In X. Liu et al. (Eds.), Energy Materials 2017 (pp. 355-365). Springer, Cham. | Publication | 2016 |
| Usov, I. O., Won, J., Devlin, D. J., Jiang, Y.-B., Valdez, J. A., & Sickafus, K. E. (2011). A novel method for incorporating fission gas elements into solids. Journal of Nuclear Materials, 408(2), 205-208. | Publication | FY2012 |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Cole, J. I., OHolleran, T. P., Keiser, D. D., Jr., & Kennedy, J. R. (2011). Out-of-pile effects of lanthanides on fuel-cladding compatibility. Journal of Nuclear Materials. | 2011 | |
| Wright, A. E., Hayes, S. L., Bauer, T. H., Chichester, H. J., Hofman, G. L., Kennedy, J. R., Kim, T. K., Kim, Y. S., Mariani, R. D., Pointer, W. D., Yacout, A. M., & Yun, D. (2012). Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview. Transactions, 106(1), 1102-1105. In Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I. Chicago, IL, 24-28 June 2012. | Publication | FY2012 |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Cole, J. I., T. P. OHolleran, D. D. Keiser Jr., and J. R. Kennedy, Out-of-pile Effects of Lanthanides on Fuel-Cladding Compatibility, submitted to Journal of Nuclear Materials. | 2010 | |
| Anderoglu, O., Byun, T. S., Toloczko, M., et al. (2013). Mechanical performance of ferritic martensitic steels for high dose applications in advanced nuclear reactors. Metallurgical and Materials Transactions A, 44(Suppl 1), 70-83. | Publication | FY2013 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | 2014 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Cologna, M., Rashkova, B., & Raj, R. (2010). Flash sintering of nanograin zirconia in <5 s at 850°C. Journal of the American Ceramic Society, 93(11), 3556-3559. | Publication | 2016 |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients. Annals of Nuclear Energy, 62, 538-547. | Publication | FY2013 |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Craft, A. E., Chichester, D. L., Papaioannou, G. C., & Williams, W. J. (2015). Qualification of a neutron computed radiography system FY-15 status report (INL/LTD-15-36644). Idaho National Laboratory. | 2015 | |
| Brown, N. R., Ludewig, H., Aronson, A., Raitses, G., & Todosow, M. (2013). Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback. Annals of Nuclear Energy, 62, 548-557. | Publication | FY2013 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | 2015 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Crapps, J., DeCroix, D. S., Galloway, J. D., Korzekwa, D. A., Aikin, R., Fielding, R., Kennedy, R., & Unal, C. (2013). Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys. Journal of Nuclear Materials, 443(1-3), 176-184. | Publication | 2013 |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Csontos, A., Whitt, J., Carmack, J., Gavrilas, M., Williams, J., & Lahoda, E. (2018, June 18-21). Panel discussion on ATF implementation in the nuclear industry. In Proceedings of the American Nuclear Society (ANS) Meeting, Philadelphia, PA. | 2018 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | FY2013 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | 2014 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | FY2013 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Curnutt, B. J., & Beausoleil, G. L. (2019, June). The Fission Accelerated Steady State Test (FAST) A revised capsule design for the accelerated testing of advanced reactor fuels. In Proceedings of the American Nuclear Society (ANS) Annual Meeting, Minneapolis, MN. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | FY2013 |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Czerniak, L., Lahoda, E., Sivack, M., Lyons, J., Byers, W., Wang, G., Oelrich, R., Xu, P., & Lu, R. (2019, September). Development of silicon carbide as a nuclear fuel cladding. Submitted to TopFuel 2019, Seattle, WA. | 2019 | |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | FY2013 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Dabney, T., Johnson, G., Maier, B., Yeom, H., & Sridharan, K. (2019, June). Development of cold spray FeCrAl coatings for accident tolerant fuel. In Proceedings of the 2019 American Nuclear Society Annual Conference, 120(1), 387-390, Minneapolis, MN. | Publication | 2019 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | FY2013 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dabney, T., Johnson, G., Yeom, H., Maier, B., Walters, J., & Sridharan, K. (2019). Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding. Nuclear Materials and Energy, 21, 100715. | Publication | 2019 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dahl, P., Kaus, I., Zhao, Z., Johnsson, M., Nygren, M., Wiik, K., Grande, T., & Einarsrud, M.-A. (2007). Densification and properties of zirconia prepared by three different sintering techniques. Ceramics International, 33(8), 1603-1610. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Dancausse, J.-P., Gering, E., Heathman, S., Benedict, U., Gerward, L., Olsen, S. S., & Hulliger, F. (1992). Compression study of uranium borides UB2, UB4 and UB12 by synchrotron X-ray diffraction. Journal of Alloys and Compounds, 189(2), 205-208. | Publication | 2018 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | 2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology to determine the aging of silicon containing materials for Generation IV nuclear reactors. AIP Conference Proceedings, 1335, 1200Â1207. Melville, NY, 2012. | Publication | FY2013 |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Davis, C. B., & Woolstenhulme, N. E. (2016). Validation of a RELAP5-3D point kinetics model of TREAT. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1-5, 2016. | 2016 | |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Daw, J. E., Rempe, J. L., & Knudson, D. L. (2012). Hot wire needle probe for in-reactor thermal conductivity measurement. IEEE Sensors Journal, 12(8), 2554-2560. | Publication | 2013 |
| Mariani, R. D., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2012). Metallic fuels: The EBR-II legacy and recent advances. Procedia Chemistry, 7, 513-520. | Publication | FY2013 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Rempe, J. L., & Wilkins, S. C. & Idaho National Laboratory (United States) (2002). Ultrasonic thermometry for in-pile temperature detection. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2002), Las Vegas, NV, United States. | Publication | 2011 |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Daw, J. E., Unruh, T. C., Durtschi, B. P., Barrett, K. E., Woolum, C. T., Smith, J. A., & Chichester, H. J. M. (2016). Instrumentation for accident tolerant fuel loop testing at ATR. In Enlarged Halden Programme Group Meeting 2016 Proceedings, May 2016. | 2016 | |
| Morris, C., Bourke, M., Byler, D., Chen, C., Hogan, G., Hunter, J., Kwiatkowski, K., Mariam, F., McClellan, K. J., Merrill, F., Morley, D., & Saunders, A. (2013). Qualitative comparison of bremsstrahlung X-rays and 800 MeV protons for tomography of urania fuel pellets. Review of Scientific Instruments, 84(2), 023902-1-7. | Publication | FY2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| Daw, J., Rempe, J., Palmer, J., Ramuhalli, P., Montgomery, R., Chien, H.-T., Tittmann, B., Reinhardt, B., & Kohse, G. (2013). Irradiation testing of ultrasonic transducers. In 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA) (pp. 1-7). Marseille, France. Invited paper for ANIMMA 2013 Special Edition. | Publication | 2013 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| de Almeida, V. F., Hunt, R. D., & Collins, J. L. (2010). Pneumatic drop-on-demand generation for production of metal oxide microspheres by internal gelation. Journal of Nuclear Materials, 404(1), 44-49. | Publication | 2010 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G. M., Shedder, J., Zhang, J., Bacalski, C., Stone, J. G., Shih, C., Vasudevamurthy, G., Lahoda, E., & Back, C. A. (2018, January 23). Development of engineered SiC-SiC accident tolerant fuel cladding. In Proceedings of the 42nd International Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Deck, C. P., Khalifa, H. E., Jacobsen, G., Sheeder, J., Shapovalov, K., Gonderman, S., Song, E., Gazza, J., Back, C. A., Xu, P., Boylan, F., & Jacko, R. (2018, September 30 - October 4). Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Demuynck, M., Erauw, J.-P., Van der Biest, O., Delannay, F., & Cambier, F. (2012). Densification of alumina by SPS and HP: A comparative study. Journal of the European Ceramic Society, 32(9), 1957-1964. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Deng, Y., Shirvan, K., Wu, Y., & Su, G. (2018). Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials, 507, 24-37. | Publication | 2018 |
| Usov, I. O., Dickerson, R. M., Dickerson, P. O., Hawley, M. E., Byler, D. D., & McClellan, K. J. (2013). Thin uranium dioxide films with embedded xenon. Journal of Nuclear Materials, 437(1-3), 1-5. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Di Lemma, F., et al. (2019, November 17-21). Metallic fast reactor separate effect studies for fuel safety. Paper presented at the American Nuclear Society Winter Meeting, Washington, D.C. | 2019 | |
| Wei, C.-C., Aitkaliyeva, A., Luo, Z., Ewh, A., Sohn, Y. H., Kennedy, J. R., Sencer, B. H., Myers, M. T., Martin, M., Wallace, J., General, M. J., & Shao, L. (2013). Understanding the phase equilibrium and irradiation effects in FeÂZr diffusion couples. Journal of Nuclear Materials, 432(1-3), 205-211. | Publication | FY2013 |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Di Lemma, F., et al. (2019, October 6-10). Metallic fast reactor separate effect studies for fuel safety. Paper presented at MiNES (Materials in Nuclear Energy Systems), Baltimore, MD. | 2019 | |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Domitr, P., Cheng, L.-Y., Kohut, P., & Ramsey, J. (2017). Development of TRACE model based on TRAC-M input for PWR LOCA analysis. In Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017. | Publication | 2017 |
| Xing, C., Jensen, C., Hua, Z., Ban, H., Hurley, D. H., Khafizov, M., & Kennedy, J. R. (2012). Parametric study of the frequency-domain thermoreflectance technique. Journal of Applied Physics, 112(10), 103105. | Publication | FY2013 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Doyle, P., Raiman, S., Rebak, R., & Terrani, K. (2017). Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding. In Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. | Publication | 2017 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Dryepondt, S., Massey, C. P., Gussev, M. N., Linton, K. D., & Terrani, K. A. (2018). Tensile strength and steam oxidation resistance of ODS FeCrAl sheet and tubes (ORNL Report TM-2018/870). Oak Ridge National Laboratory. | Publication | 2018 |
| Besmann, T. M., Ferber, M. K., Lin, H.-T., & Collin, B. P. (2014). Fission product release and survivability of UN-kernel LWR TRISO fuel. Journal of Nuclear Materials, 448(1-3), 412-419. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Dryepondt, S., Massey, C., & Edmonson, P. (2016). Oak Ridge National Laboratory report on 2nd generation ODS FeCrAl alloy development for accident-tolerant fuel cladding, ORNL-TM-2016/456, Oak Ridge National Laboratory, August 26, 2016. | Publication | 2016 |
| Bragg-Sitton, S. (2014). Development of advanced accident-tolerant fuels for commercial LWRs. Nuclear News, 57, 83-91. | Publication | FY2014 |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Dryepondt, S., Massey, C., & Gussev, M. N. (2017). Production and characterization of large batch FeCrAl ODS alloy (ORNL/TM-2017/445). Oak Ridge National Laboratory. | 2017 | |
| Bragg-Sitton, S. (2014). Development of enhanced accident-tolerant fuels for light water reactors. In 2015 McGraw-Hill Yearbook of Science & Technology. | FY2014 | |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Dryepondt, S., Unocic, K. A., Hoelzer, D. T., Massey, C. P., & Pint, B. A. (2018). Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding. Journal of Nuclear Materials, 501, 59-71. | Publication | 2018 |
| Bragg-Sitton, S., Merrill, B., Teague, M., Ott, L., Robb, K., Farmer, M., Billone, M., Montgomery, R., Stanek, C., Todosow, M., & Brown, N. (2014). Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics (INL/EXT-13-29957 and FCRD-FUEL-2013-000264). Idaho National Laboratory. | Publication | FY2014 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Edmondson, P. D., Briggs, S. A., Yamamoto, Y., Howard, R. H., Sridharan, K., Terrani, K. A., & Field, K. G. (2016). Irradiation-enhanced ?? precipitation in model FeCrAl alloys. Scripta Materialia, 116, 112-116. | Publication | 2016 |
| Brown, N. R., Aronson, A., Todosow, M., Brito, R., & McClellan, K. J. (2014). Neutronic performance of uranium nitride composite fuels in a PWR. Nuclear Engineering and Design, 275, 393-407. | Publication | FY2014 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Eftink, B. P., Quintana, M. E., Romero, T. J., et al. (2020). Shear punch testing of neutron-irradiated HT-9 and 14YWT. JOM, 72, 17031709. | Publication | 2019 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Mariani, R. D., Hartmann, T., Porter, D. L., Hayes, S. L., & Kennedy, J. R. (2013). Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples. Journal of Nuclear Materials, 432(1-3), 539-544. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Egeland, G. W., Valdez, J. A., Maloy, S. A., McClellan, K. J., Sickafus, K. E., & Bond, G. M. (2013). Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption. Journal of Nuclear Materials, 435(1-3), 77-87. | Publication | 2013 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Motta, A. T., Weidner, R., Anderson, T., & Ecker, L. E. (2016). Sample environment for in situ synchrotron corrosion studies of materials in extreme environments. Review of Scientific Instruments, 87(10), 105122. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Elbakhshwan, M. S., Gill, S. K., Rumaiz, A. K., Bai, J., Ghose, S., Rebak, R. B., & Ecker, L. E. (2017). High-temperature oxidation of advanced FeCrNi alloy in steam environments. Applied Surface Science, 426, 562-571. | Publication | 2016 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Farmer, M. T., Leibowitz, L., Terrani, K. A., & Robb, K. R. (2014). Scoping assessments of ATF impact on late-stage accident progression including molten coreconcrete interaction. Journal of Nuclear Materials, 448(13), 534-540. | Publication | 2014 |
| Carmack, J. (2014). Accident tolerant fuel development program. Nuclear Plant Journal, 46(1), January-February. | FY2014 | |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Farzbod, F., & Hurley, D. H. (2012). Resonant ultrasound spectroscopy: Using mode shapes. IEEE Transactions on Ultrasonics, Ferroelectrics, and Frequency Control, 59(11), 2413-2421. | Publication | 2012 |
| Collin, B. P. (2014). Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code. Journal of Nuclear Materials, 451(1-3), 65-77. | Publication | FY2014 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Fernandez, J. C., Gautier, D. C., Huang, C., Palaniyappan, S., Albright, B. J., Bang, W., Dyer, G., Favalli, A., Hunter, J. F., Mendez, J., Roth, M., Swinhoe, M., Bradley, P. A., Deppert, O., Espy, M., Falk, K., Guler, N., Hamilton, C., Hegelich, B. M., ... Yin, L. (2017). Laser-plasmas in the relativistic transparency regime: Science and applications. Physics of Plasmas, 24(5), 056. | Publication | 2017 |
| Cunningham, N. J., Wu, Y., Etienne, A., Haney, E. M., Odette, G. R., Stergar, E., Hoelzer, D. T., Kim, Y. D., Wirth, B. D., & Maloy, S. A. (2014). Effect of bulk oxygen on 14YWT nanostructured ferritic alloys. Journal of Nuclear Materials, 444(1-3), 35-38. | Publication | FY2014 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status of FeCrAl ODS irradiations in the High Flux Isotope Reactor (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., & Howard, R. H. (2016). Status report on irradiation capsules, designed to evaluate FeCrAl-UO2 interactions (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/267). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Barrett, K., Sun, Z., & Yamamoto, Y. (2016). Submission of FeCrAl feedstock for support of AFC ATF-2 irradiations (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/394). September 2016. Oak Ridge National Laboratory. | Publication | 2016 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | FY2014 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| Field, K. G., Briggs, S. A., Edmondson, P. D., Haley, J. C., Howard, R. H., Hu, X., Littrell, K. C., Parish, C. M., & Yamamoto, Y. (2016). Database on performance of neutron irradiated FeCrAl alloys (FY-16 DOE-NE FCRD Report: ORNL/TM-2016/335). Oak Ridge National Laboratory. | Publication | 2016 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | FY2014 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K. G., Hu, X., Littrell, K. C., Yamamoto, Y., & Snead, L. L. (2015). Radiation tolerance of neutron-irradiated model FeCrAl alloys. Journal of Nuclear Materials, 465, 746-755. | Publication | 2015 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Field, K., Snead, M., Yamamoto, Y., & Terrani, K. (2017). Handbook of the materials properties of FeCrAl alloys for nuclear power production applications (ORNL/TM-2017/186, Rev. 1). Oak Ridge National Laboratory. | Publication | 2017 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | FY2014 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Fink, J. K. (2000). Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 279(1), 1-18. | Publication | 2018 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Folsom, C. P., Jensen, C. B., Williamson, R. L., Woolstenhulme, N. E., Ban, H., & Wachs, D. M. (2016). BISON modeling of reactivity-initiated accident experiments in a static environment. In Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance (pp. 239-247). Boise, Idaho, USA, Sept. 11-16, 2016. | Publication | 2016 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | FY2014 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Franceschini, F., King, J., Lahoda, E., Oelrich, B., & Ray, S. (2018, April 22-28). Implementation of Westinghouse ATF to extend cycle length of current PWR to 24-month cycles. In Reactor physics paving the way towards more efficient systems (PHYSOR 2018). Cancun, Q. R. (Mexico): Sociedad Nuclear Mexicana. | Publication | 2018 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Pressureless joining of SiC by transient eutectic-phase method. Transactions of the American Nuclear Society, 110(1), 863-864. | Publication | FY2014 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Franceschini, F., Kucukboyaci, V., Stucker, D., Lahoda, E. J., & Karouta, Z. (2019, September 22-27). Modeling of Westinghouse advanced fuels EnCore and ADOPT with the CASL tools. In Proceedings of TopFuel 2019, Seattle, WA, 153-160. | Publication | 2019 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2014). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. In Ceramic Materials for Energy Applications IV (pp. 151-160). | Publication | FY2014 |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Frazer, D., White, J. T., & Saleh, T. A. (2019). Nanomechanical properties of high uranium density fuels (Report No. NTRD-M3FT-19LA020201026, LA-UR-19-27315). Los Alamos National Laboratory. | 2019 | |
| Mosbrucker, P. L., Brown, D. W., Anderoglu, O., Balogh, L., Maloy, S. A., Sisneros, T. A., Almer, J., Tulk, E. F., Morgenroth, W., & Dippel, A. C. (2013). Neutron and X-ray diffraction analysis of the effect of irradiation dose and temperature on microstructure of irradiated HT-9 steel. Journal of Nuclear Materials, 443(1-3), 522-530. | Publication | FY2014 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Galloway, J., & Unal, C. (2016). Accident-tolerant-fuel performance analysis of APMT steel clad/UO2 fuel and APMT steel clad/UN-U3Si5 fuel concepts. Nuclear Science and Engineering, 182(4), 523537. | Publication | 2015 |
| Nelson, A. T., Rittman, D. R., White, J. T., Dunwoody, J. T., Kato, M., & McClellan, K. J. (2014). An evaluation of the thermophysical properties of stoichiometric CeO2 in comparison to UO2 and PuO2. Journal of the American Ceramic Society, 97(11), 3652-3659. | Publication | FY2014 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Galloway, J., Unal, C., Carlson, N., Porter, D., & Hayes, S. (2015). Modeling constituent redistribution in UPuZr metallic fuel using the advanced fuel performance code BISON. Nuclear Engineering and Design, 286, 1-17. | Publication | 2015 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Garrison, B., Howell, M., Cinbiz, M. N., Gussev, M., & Linton, K. (2019, September 22-27). Length-dependence of severe accident test station integral testing. Results from this work presented presented at the 2019 ANS Top Fuel Conference, Seattle WA. | Publication | 2019 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Ge, L., Subhash, G., Baney, R. H., Tulenko, J. S., & McKenna, E. (2013). Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS). Journal of Nuclear Materials, 435(1-3), 1-9. | Publication | 2016 |
| Pint, B. A., Dryepondt, S., Unocic, K. A., & Hoelzer, D. T. (2014). Development of ODS FeCrAl for compatibility in fusion and fission energy applications. JOM, 66(12), 2458-2466. | Publication | FY2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Maldonado, I., Terrani, K., Godfrey, A., Gehin, J., & Powers, J. (2014). Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors. Nuclear Technology, 188(3), 238251. | Publication | 2014 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Powers, J. J., Maldonado, G. I., Worrall, A., & Terrani, K. A. (2015). Demonstration of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs. In Proceedings of Advances in Nuclear Fuel Management V (ANFM V) (p. 31). Hilton Head Island, South Carolina, USA, March 29 April 1, 2015. | Publication | 2015 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| George, N. M., Sweet, R. T., Maldonado, G. I., Wirth, B. D., Powers, J. J., & Worrall, A. (2015). Fuel performance calculations for FeCrAl cladding in BWRs. Transactions of the American Nuclear Society, 113, 553-556. | Publication | 2016 |
| Teague, M., & Gorman, B. (2014). Utilization of dual-column focused ion beam and scanning electron microscope for three-dimensional characterization of high burn-up mixed oxide fuel. Progress in Nuclear Energy, 72, 67-71. | Publication | FY2014 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | 2015 |
| Teague, M., Gorman, B., King, J., Porter, D., & Hayes, S. (2013). Microstructural characterization of high burn-up mixed oxide fast reactor fuel. Journal of Nuclear Materials, 441(1-3), 267-273. | Publication | FY2014 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Gigax, J. G., Kim, H., Aydogan, E., Price, L. M., Wang, X., Maloy, S. A., Garner, F. A., & Shao, L. (2019). Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 444, 68-73. | Publication | 2019 |
| Teague, M., Gorman, B., Miller, B., & King, J. (2014). EBSD and TEM characterization of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 475-480. | Publication | FY2014 |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Gofryk, K. (2017, March). Unusual thermal behavior of uranium dioxide fuel. Invited talk at the 47èmes Journées des Actinides, Karpacz, Poland. | 2017 | |
| Teague, M., Tonks, M., Novascone, S., & Hayes, S. (2014). Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel. Journal of Nuclear Materials, 444(1-3), 161-169. | Publication | FY2014 |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Gofryk, K. (2018). Effect of off-stoichiometry and grain size on thermal transport in uranium dioxide. Talk given at the Nuclear Materials Conference (NuMat 2018), Seattle, WA. | 2018 | |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Golovchenko, Y. M. (2011). Some results of developments and investigations of fuel pins with metal fuel for heterogeneous core of fast reactors of the BN-type. Energy Procedia, 7, 205-212. | Publication | 2017 |
| Unocic, K. A., Hoelzer, D. T., & Pint, B. A. (2015). Microstructure and environmental resistance of low Cr ODS FeCrAl. Materials at High Temperatures, 32(1-2), 123-132. | Publication | FY2014 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Grote, C. (2019, July 17). Assessment of viability of scaled annular pellet fabrication technologies (Report No. LA-UR-19-27197). Los Alamos National Laboratory. | Publication | 2019 |
| Was, G. S., Jiao, Z., Getto, E., Sun, K., Monterrosa, A. M., Maloy, S. A., Anderoglu, O., Sencer, B. H., & Hackett, M. (2014). Emulation of reactor irradiation damage using ion beams. Scripta Materialia, 88, 33-36. | Publication | FY2014 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gurgen, A., & Shirvan, K. (2018). Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings. Nuclear Engineering and Design, 337, 38-50. | Publication | 2018 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | 2015 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Harp, J. M., Hayes, S. L., Medvedev, P. G., Porter, D. L., & Capriotti, L. (2017). Testing fast reactor fuels in a thermal reactor: A comparison report (INL/EXT-17-41677 [NTRDFUEL-2017-000148], Rev. 0). Idaho National Laboratory. | Publication | 2017 |
| Bailey, N. A., Stergar, E., Toloczko, M., & Hosemann, P. (2015). Atom probe tomography analysis of high dose MA957 at selected irradiation temperatures. Journal of Nuclear Materials, 459, 225-234. | Publication | FY2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | 2015 |
| Baker, C., Housley, G. K., Imholte, D. D., & Woolstenhulme, N. E. (2015). HFEF support equipment determination report for the TREAT water loop (INL/LTD-15-36111). Idaho National Laboratory. | FY2015 | |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Harp, J. M., Porter, D. L., Miller, B. D., Trowbridge, T. L., & Carmack, W. J. (2017). Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. Journal of Nuclear Materials, 494, 227-239. | Publication | 2017 |
| Barabash, R. I., Voit, S. L., Aidhy, D. S., Lee, S. M., Knight, T. W., Sprouster, D. J., & Ecker, L. E. (2015). Cation and vacancy disorder in U1-yNdyO2.00-x alloys. Journal of Materials Research, 30(11), 3026-3040. | Publication | FY2015 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| He, L. F., Pakarinen, J., Kirk, M. A., Gan, J., Nelson, A. T., Bai, X.-M., El-Azab, A., & Allen, T. R. (2014). Microstructure evolution in Xe-irradiated UO2 at room temperature. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 330, 55-60. | Publication | 2014 |
| Barrett, K. E., Ellis, K. D., Glass, C. R., Roth, G. A., Teague, M. P., & Johns, J. (2015). Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests. Nuclear Engineering and Design, 294, 38-51. | Publication | FY2015 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L., Harp, J. M., Hoggan, R. E., & Wagner, A. R. (2017). Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C. Journal of Nuclear Materials, 486, 274-282. | Publication | 2017 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| He, L.-F., Gupta, M., Yablinsky, C. A., Gan, J., Kirk, M. A., Bai, X.-M., Pakarinen, J., & Allen, T. R. (2013). In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal. Journal of Nuclear Materials, 443(1-3), 71-77. | Publication | 2014 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C. H., & Li, X. (2018, October 15). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Presentation delivered at the MS&T18 Conference, Columbus, OH. | Publication | 2019 |
| Brown, N. R., Cheng, L.-Y., & Todosow, M. (2014). Uranium nitride composite fuels in a light water reactor: Advanced cladding, nodal core calculations, and transient analysis. Transactions of the American Nuclear Society, 111(1), 1367-1370. | Publication | FY2015 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Heim, F. M., Croom, B. P., Bumgardner, C., & Li, X. (2018). Scalable measurements of tow architecture variability in braided ceramic composite tubes. Journal of the American Ceramic Society, 101(9), 4297-4307. | Publication | 2019 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Hill, C. M., Bess, J. D., & Woolstenhulme, N. E. (2017). Neutronics analysis of TREAT Multi-SERTTA calibration test vehicle (Multi-SERTTA CAL). Transactions of the American Nuclear Society, 116(1), 1073-1076. San Francisco, CA. | Publication | 2017 |
| Brown, N. R., Todosow, M., Cheng, L.-Y., & Cuadra, A. (2015). Screening of reactor performance and safety of fuel and cladding candidates with enhanced accident tolerance. In Proceedings of Top Fuel 2015 (pp. 10-20). Zurich, Switzerland, September 13-17, 2015. | Publication | FY2015 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Bess, J. D., Parry, J. R., & Housley, G. K. (2016, May 1-5). MCNP water physics scoping study to support accident tolerant fuel testing in TREAT. In Proceedings of PHYSOR 2016. American Nuclear Society, Sun Valley, Idaho. May 15, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., & Housley, G. K. (2016, September 11-16). TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle. In Proceedings of the Top Fuel 2016 Conference. Boise, Idaho, USA. Sep, 11-16, 2016 | Publication | 2016 |
| Craft, A. E., Wachs, D. M., Okuniewski, M. A., Chichester, D. L., Williams, W. J., Papaioannou, G. C., & Smolinski, A. T. (2015). Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory. Physics Procedia, 69, 483-490. | Publication | FY2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | 2015 |
| Davis, C. B., & Woolstenhulme, N. E. (2015, August 10-12). Validation of a RELAP5-3D point kinetics model of TREAT. Paper presented at the 2015 International RELAP Users Group Meeting, Idaho Falls, ID. | Publication | FY2015 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hoggan, R., Harp, J., & He, L. (2017). Interdiffusion behavior of U3Si2 and FeCrAl via diffusion couple studies. Transactions of the American Nuclear Society, 116(1), 403-406. | Publication | 2017 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Ang, C. K., Singh, G., & Katoh, Y. (2016). Technique development for modulus, microcracking, hermeticity, and coating evaluation capability characterization of SiC/SiC tubes ORNL/TM-2016/372, Oak Ridge National Laboratory. | Publication | 2016 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | 2015 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Hua, Z., Ban, H., Khafizov, M., Schley, R., Kennedy, J. R., & Hurley, D. H. (2012). Spatially localized measurement of thermal conductivity using a hybrid photothermal technique. Journal of Applied Physics, 111(11), 113505. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| Huang, K., Park, Y., Ewh, A., Sencer, B. H., Kennedy, J. R., Coffey, K. R., & Sohn, Y. H. (2012). Interdiffusion and reaction between uranium and iron. Journal of Nuclear Materials, 424(1-3), 82-88. | Publication | 2012 |
| George, N. M., Terrani, K., Powers, J., Worrall, A., & Maldonado, I. (2015). Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors. Annals of Nuclear Energy, 75, 703-712. | Publication | FY2015 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Huang, Z., Harris, A., Maloy, S. A., & Hosemann, P. (2014). Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy. Journal of Nuclear Materials, 451(13), 162-167. | Publication | 2014 |
| Gussev, M. N., Byun, T. S., Yamamoto, Y., Maloy, S. A., & Terrani, K. A. (2015). In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding. Journal of Nuclear Materials, 466, 417-425. | Publication | FY2015 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Hull, L. C., Barrett, K. E., Lybeck, N., Johnson, N., Galbraith, S. G., Core, G. M., & Chichester, J. M. (2016, September). NDMAS implementation and data qualification for accident tolerant fuel experiments. Paper presented at the ANS Top Fuel 2016 Meeting, Boise, ID. Paper number 16-50375. | Publication | 2016 |
| Harp, J. M., Lessing, P. A., & Hoggan, R. E. (2015). Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation. Journal of Nuclear Materials, 466, 728-738. | Publication | FY2015 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hunt, R. D., Hunn, J. D., Birdwell, J. F., Lindemer, T. B., & Collins, J. L. (2010). The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process. Journal of Nuclear Materials, 401(1-3), 55-59. | Publication | 2010 |
| Hoelzer, D. T., Unocic, K. A., Sokolov, M. A., & Byun, T. S. (2016). Influence of processing on the microstructure and mechanical properties of 14YWT. Journal of Nuclear Materials, 471, 251-265. | Publication | FY2015 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hunt, R. D., Montgomery, F. C., & Collins, J. L. (2010). Treatment techniques to prevent cracking of amorphous microspheres made by the internal gelation process. Journal of Nuclear Materials, 405(2), 160-164. | Publication | 2010 |
| Hu, X., Terrani, K. A., Wirth, B. D., & Snead, L. L. (2015). Hydrogen permeation in FeCrAl alloys for LWR cladding application. Journal of Nuclear Materials, 461, 282-291. | Publication | FY2015 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Hurley, D. H., Khafizov, M., Shinde, S., & Hurley, D. (2011). Measurement of Kapitza resistance across a bicrystal interface. Journal of Applied Physics, 109(8), 083504. | Publication | 2011 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Hurley, D. H., Reese, S. J., & Farzbod, F. (2012). Application of laser-based resonant ultrasound spectroscopy to study texture in copper. Journal of Applied Physics, 111(5), 053527. | Publication | 2012 |
| Koyanagi, T., Kiggans, J., Shih, C., & Katoh, Y. (2015). Processing and characterization of diffusion-bonded silicon carbide joints using molybdenum and titanium interlayers. Ceramic Engineering and Science Proceedings, 35(7), 151-160. | Publication | FY2015 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Hurley, D. H., Reese, S. J., Park, S. K., Utegulov, Z., Kennedy, J. R., & Telschow, K. L. (2010). In situ laser-based resonant ultrasound measurements of microstructure mediated mechanical property evolution. Journal of Applied Physics, 107(6), 063510. | Publication | 2010 |
| Lim, H. C., K. Rudman, K. Krishnan, R. McDonald, P. Peralta, P. Dickerson, D. Byler, C. Stanek, K. J. McClellan. Microstructurally Explicit Study of Transport Phenomena In Uranium Oxide. In TMS 2014: 143rd Annual Meeting & Exhibition, Annual Meeting Supplemental Proceedings (pp. 1041-1047). Springer, Cham. | Publication | FY2015 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Hurley, D., Khafizov, M., Kennedy, R., & Burgett, E. (2013). Mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics. Proceedings of the 2013 International Congress on Ultrasonics, 686. Siong, G.W., Piang L.S., Cheong, K.B. eds., May 2-5, 2013. | Publication | 2013 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Isler, J., Zhang, J., Mariani, R., & Unal, C. (2017). Experimental solubility measurements of lanthanides in liquid alkalis. Journal of Nuclear Materials, 495, 438-441. | Publication | 2017 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Kennedy, J. R. (2010). As-cast microstructures in UPuZr alloy fuel pins with 58 wt.% minor actinides and 01.5 wt% rare-earth elements. Materials Characterization, 61(11), 1194-1202 | Publication | 2011 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Janney, D. E., & Papesch, C. A. (2016). An introduction to the FCRD transmutation fuels handbook 2015. Transactions of the American Nuclear Society, 114(1), 1077-1080. Presented at the 2016 Transactions of the American Nuclear Society Annual Meeting (ANS 2016), New Orleans, United States, June 12-16, 2016. | Publication | 2016 |
| Nelson, A. T., White, J. T., Byler, D. D., Dunwoody, J. T., Valdez, J. A., & McClellan, K. J. (2014). Overview of properties and performance of uranium-silicide compounds for light water reactor applications. Transactions of the American Nuclear Society, 110(1), 987-989. | Publication | FY2015 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Janney, D. E., & Sencer, B. H. (2017). Microstructure changes caused by annealing of U-Pu-Zr alloys. Journal of Nuclear Materials, 486, 66-69. | Publication | 2017 |
| Parish, C. M., Field, K. G., Certain, A. G., & Wharry, J. P. (2015). Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys. Journal of Materials Research, 30(9), 1275-1289. | Publication | FY2015 |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| J.Bischoff, C.Vauglin, P. Barberis, C., Roubeyrie, D. Perche, D. Duthoo,, F.Schuster, J-C. Brachet, K. Nimishakavi, AREVA NPs Enhanced Accident Tolerant, Fuel Developments: Focus on Cr-Coated, M5TM Cladding, 2017 Water Reactor Fuel, Performance Meeting, Korea,, September 2017 | 2017 | |
| Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metallurgical and Materials Transactions E, 2, 190-196. | Publication | FY2015 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Jensen, C. B., Davis, C. B., Woolstenhulme, N. E., OBrien, R. C., & Wachs, D. M. (2016). Thermal-hydraulic response of the TREAT multi-vessel static environment test vehicle. In Proceedings of the PHYSOR-2016 Conference, Sun Valley, Idaho, USA, May 1 5, 2016. | Publication | 2016 |
| Pint, B. A., Unocic, K. A., & Terrani, K. A. (2015). Effect of steam on high temperature oxidation behaviour of alumina-forming alloys. Materials at High Temperatures, 32(1-2), 28-35. | Publication | FY2015 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Jensen, C. B., Folsom, C. P., Davis, C. B., Woolstenhulme, N. E., Bess, J. D., OBrien, R. C., Ban, H., & Wachs, D. M. (2016). Thermal-hydraulic performance of the TREAT Multi-SERTTA for reactivity-initiated accident experiments. In Proceedings of ANS Top Fuel 2016 Conference, Boise, ID. Sep, 11-16, 2016. | Publication | 2016 |
| Porter, D. L., Chichester, H. J. M., Medvedev, P. G., Hayes, S. L., & Teague, M. C. (2015). Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials, 465, 464-470. | Publication | FY2015 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C. B., Woolstenhulme, N. E., & Wachs, D. M. (2017, September 10-14). Fuel-coolant interaction results for high energy in-pile LWR fuels experiments. In Proceedings of Water Reactor Fuel Performance Meeting 2017, Jeju Island, South Korea. | Publication | 2017 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Jensen, C., Davis, C., & Woolstenhulme, N. (2015, June 7-11). Thermal analysis of TREAT experimental devices. Transactions of the American Nuclear Society, 112(1), 372. San Antonio TX. | Publication | 2015 |
| Robb, K. R. (2015). Analysis of the FeCrAl accident tolerant fuel concept benefits during BWR station blackout accidents. In Proceedings of NURETH-16. Chicago, IL, USA, August 30-September 4, 2015. | Publication | FY2015 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactor. Journal of Nuclear Materials, 504, 122-134. | Publication | 2019 |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Jolly, B., Kato, Y., Lowden, R., Nelson, A., Schumacher, A., & Cooley, K. (2019). Development of vapor processing capability for advanced SiC/SiC composites (Milestone Report No. ORNL/SPR-2019/1125). Oak Ridge National Laboratory. | 2019 | |
| Shih, C., Katoh, Y., Kiggans, J., Koyanagi, T., Khalifa, H. E., Back, C. A., Hinoki, T., & Ferraris, M. (2015). Comparison of shear strength of ceramic joints determined by various test methods with small specimens. Ceramic Engineering and Science Proceedings, 35(7), 139-149. | Publication | FY2015 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Jossou, E., Malakkal, L., Szpunar, B., Oladimeji, D., & Szpunar, J. A. (2017). A first principles study of the electronic structure, elastic and thermal properties of UB2. Journal of Nuclear Materials, 490, 41-48. | Publication | 2018 |
| Shih, C., Katoh, Y., Ozawa, K., Lara-Curzio, E., & Snead, L. (2015). Through thickness mechanical properties of chemical vapor infiltration and nano-infiltration and transient eutectic-phase processed SiC/SiC composites. International Journal of Applied Ceramic Technology, 12(3), 481-490. | Publication | FY2015 |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Karoutas, Z. E., Schneider, R., LaBarge, N. R., Romero, J., & Xu, P. (2017, September 10-14). Westinghouse accident tolerant fuel plant benefits. Paper presented at the 2017 Water Reactor Fuel Performance Meeting, Jeju Island, South Korea. | 2017 | |
| Silva, C. M., Hunt, R. D., Snead, L. L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Karoutas, Z., Luangdilok, W., Shockling, M., Schneider, R., Lahoda, E., & Xu, P. (2018). Update on Westinghouse benefits of ENCORE® fuel. In Proceedings of the TopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018. | Publication | 2018 |
| Silva, C. M., Katoh, Y., Voit, S. L., & Snead, L. L. (2015). Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures. Journal of Nuclear Materials, 460, 52-59. | Publication | FY2015 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Kato, M., Murakami, T., Sunaoshi, T., Nelson, A. T., & McClellan, K. J. (2013). Property measurements of (U0.7Pu0.3)O2-x in PO2-controlled atmosphere. In Proceedings of the International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 (pp. 852-856). Salt Lake City, UT, United States, September 29 - October 2, 2013. | Publication | 2014 |
| Silva, C. M., Lindemer, T. B., Voit, S. R., Hunt, R. D., Besmann, T. M., Terrani, K. A., & Snead, L. L. (2014). Characteristics of uranium carbonitride microparticles synthesized using different reaction conditions. Journal of Nuclear Materials, 454(1-3), 405-412. | Publication | FY2015 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Katoh, Y., Snead, L. L., Cheng, T., Shih, C., Lewis, W. D., Koyanagi, T., Hinoki, T., Henager, C. H., & Ferraris, M. (2014). Radiation-tolerant joining technologies for silicon carbide ceramics and composites. Journal of Nuclear Materials, 448(13), 497-511. | Publication | 2014 |
| Silva, C., Hunt, R., Snead, L., & Terrani, K. A. (2015). Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry, 54(1), 293-298. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Katoh, Y., Terrani, K. A., & Snead, L. L. (2014). Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures. ORNL/TM-2014/210, Revision 1, Oak Ridge National Laboratory. | Publication | 2014 |
| Snead, L. L., Katoh, Y., & Terrani, K. (2015). Discussion of minimum stress allowables for SiC composite cladding. Transactions of the American Nuclear Society, 112(1), 280-283. | Publication | FY2015 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Katoh, Y., Terrani, K. A., Koyanagi, T., Petrie, C. M., Singh, G., Snead, L. L., & Deck, C. (2016). Irradiation high heat flux synergism in silicon carbide-based fuel claddings for light water reactors. In Proceedings of Top Fuel 2016 (pp. 823-831). | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Khafizov, M., Pakarinen, J., He, L., Henderson, H. B., Manuel, M. V., Nelson, A. T., Jaques, B. J., Butt, D. P., & Hurley, D. H. (2016). Subsurface imaging of grain microstructure using picosecond ultrasonics. Acta Materialia, 112, 209-215. | Publication | 2016 |
| Terrani, K. A., & Silva, C. M. (2015). High temperature steam oxidation of SiC coating layer of TRISO fuel particles. Journal of Nuclear Materials, 460, 160-165. | Publication | FY2015 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Khalifa, H. E., Sheeder, J. D., Jacobsen, G. M., & Deck, C. P. (2016). Radiation tolerant joining for silicon carbide-based accident tolerant fuel cladding. In Light Water Reactor (LWR) Fuel Performance Meeting (TopFuel), 2016, Boise, Idaho, September 12-14, 2016, paper number 17517. | Publication | 2016 |
| Terrani, K. A., Kiggans, J. O., Silva, C. M., Shih, C., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. Journal of Nuclear Materials, 457, 9-17. | Publication | FY2015 |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Khalifa, H., Deck, C., Jacobsen, G., Sheeder, J., Zhang, J., Bacalski, C., Stone, J., Shih, C., Vasudevamurthy, G., Shatoff, H., Huang, X., Bao, J., Jacko, R., Lahoda, E., & Back, C. (2017, January). Development of SiC-SiC composite accident tolerant fuel cladding. Paper presented at the ICACC, Daytona Beach, FL. | 2017 | |
| Terrani, K. A., Yang, Y., Kim, Y.-J., Rebak, R., Meyer, H. M., & Gerczak, T. J. (2015). Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. Journal of Nuclear Materials, 465, 488-498. | Publication | FY2015 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| Kim, B. G., Rempe, J. L., Knudson, D. L., Condie, K. G., & Sencer, B. H. (2012). In-situ creep testing capability for the Advanced Test Reactor. Nuclear Technology, 179(3), 417428. | Publication | 2013 |
| White, J. T., Nelson, A. T., Byler, D. D., Safarik, D. J., Dunwoody, J. T., & McClellan, K. J. (2015). Thermophysical properties of U3Si5 to 1773K. Journal of Nuclear Materials, 456, 442-448. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Kim, S.-W., & Lee, B. H. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IMechanical and microstructural observations. Materials Science and Engineering: A, 559, 101-110. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., & McClellan, K. J. (2014). Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications. Transactions of the American Nuclear Society, 110(1), 840-841. | Publication | FY2015 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| Kim, J. H., Byun, T. S., Hoelzer, D. T., Park, C. H., Yeom, J. T., & Hong, J. K. (2013). Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part IIMechanistic models and predictions. Materials Science and Engineering: A, 559, 111-118. | Publication | 2013 |
| White, J. T., Nelson, A. T., Dunwoody, J. T., Byler, D. D., Safarik, D. J., & McClellan, K. J. (2015). Thermophysical properties of U3Si2 to 1773K. Journal of Nuclear Materials, 464, 275-280. | Publication | FY2015 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Kiran Kumar, N. A. P., Stevens, J. N., Savela, M., Mays, B., & Strumpell, J. (2016). AREVA enhanced accident tolerant fuel program current results and future plans. In ANS Top Fuel 2016 Meeting Proceedings, Boise, ID, September 11-15, (pp. 169-178). | Publication | 2016 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Knudson, D. L. (2012). Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing. Measurement Science and Technology, 23(2), 025604. | Publication | 2011 |
| Woolstenhulme, N. E., et al. (2015, August 25-27). ATF design for transient testing. AFC Integration Meeting, Brookhaven National Laboratory (BNL). | FY2015 | |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Knudson, D., & Rempe, J. & Idaho National Laboratory (United States) (2001). Recommendations for use of LVDTs in ATR high temperature irradiation testing. In Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2001), Las Vegas, NV, United States. | Publication | 2011 |
| Woolstenhulme, N. E., Wachs, D. M., & Beasley, A. A. (2014, November 9-13). Transient experiment design for accident tolerance fuels. Transactions of the American Nuclear Society, 111(1), 604-606, Anaheim CA. | Publication | FY2015 |
| Koenig, T. W., Olson, D. L., Mishra, B., King, J. C., Fletcher, J., Gerstenberger, L., Lawrence, S., Martin, A., Mejia, C., Meyer, M. K., Kennedy, R., Hu, L., Kohse, G., & Terry, J. (2011). Advanced non-destructive assessment technology |