2018 | AFC ACCOMPLISHMENTS 178 Author (s) Title Publication S. Dryepondt, K.A. Unocic, D.T. Hoelzer, C.P. Massey and B.A. Pint Development of Low-Cr ODS FeCrAl Alloys for Accident-tolerant Fuel Cladding Journal of Nuclear Materials 501 (2018), 59-71 S. Dryepondt, C.P. Massey, M.N. Gussev, K.D. Linton and K.A.Terrani Tensile Strength and Steam Oxidation Resistance of ODS FeCrAl Sheet and Tubes ORNL ReportTM-2018/870 (2018) J. Fink Thermophysical properties of uranium dioxide Journal of Nuclear Materials 279 (1) 1-18 (200) F. Franceschini, J. King, E. Lahoda, R. Oelrich, and S. Ray Implementation of Westinghouse ATF to Extend Cycle Length of Current PWRs to 24-month Cycles Proceedings of the PHYSOR 2018 Conference, Cancun, Mexico,Apr 22-26, 2018 D. R. Fredrickson, M. G. Barner, R.D., Chasanov, R. L. Nuttall, R. Kleb, and W. N. Hubbard The Enthalpy of Uranium Diboride from 600 to 1500° K by Drop Calo- rimetry HighTemp. Sci. 1, vol. 80, pp. 373–380, 1969. D. R. Fredrickson, R. D. Barnes, and M. G. Chasanov Enthalpy of uranium diboride from 1300 to 2300˚K by drop calorimetry HighTemp. Sci., vol. 2, pp. 299–301, 1970. K. Gofryk Effect of Off-stoichiometry and Grain Size onThermalTransport in Uranium Dioxide Talk given at the Nuclear Materials conference NuMat 2018, Seattle, WA, 2018 A.Gurgen and K. Shirvan Estimation of CopingTime in Pres- surized Water Reactors for NearTerm AccidentTolerant Fuel Claddings Nuclear Engineering and Design, 337 (2018), 38-50 E. Jossou, L. Malakkal, B. Szpunar, D. Oladimeji, and J.A. Szpunar A First Principles Study of the Elec- tronic Structure, Elastic andThermal Properties of UB2 Journal of Nuclear Matter 490 (2017), 41-48 Z. Karoutas,W. Luangdilok, M. Shock- ling, R. Schneider, E. Lahoda and P. Xu Update On Westinghouse Benefits of Encore® Fuel Proceedings of theTopFuel 2018 Conference, Prague, Czech Republic, Sep 30 - Oct 4, 2018 T. Koyanagi,Y. Katoh, G. Singh, C. Petrie, C. Deck, K.Terrani1,T. Koyanagi, Y. Katoh, G. Singh, C. Petrie, C. Deck and K.Terrani Post-irradiation Examination of SiC Tubes Neutron Irradiated Under a Radial High Heat Flux Proceedings of the 42nd Interna- tional Conference and Expo on Advanced Ceramics and Composites, Daytona Beach, Florida, January 23rd, 2018