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| 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 |
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| 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 |
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| 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 |
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| 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 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., eve ek, 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 |
| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
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| 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 |
| Kamerman, D., Cappia, F., Wheeler, K., Petersen, P., Rosvall, E., Dabney, T., Yeom, H., Sridharan, K., eve ek, 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 |
| 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 |
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| 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 |
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| 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 |