| Parametric evaluation of SiC/SiC composite cladding with UO2 fuel for LWR applications: fuel rod interactions and impact of nonuniform power profile in fuel rod G Singh, R Sweet, NR Brown, BD Wirth, Y Katoh, K Terrani Journal of Nuclear Materials 499, 155-167, 2018 | 49 | 2018 |
| Full core LOCA safety analysis for a PWR containing high burnup fuel N Capps, A Wysocki, A Godfrey, B Collins, R Sweet, N Brown, S Lee, ... Nuclear Engineering and Design 379, 111194, 2021 | 36 | 2021 |
| Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation RT Sweet, NM George, GI Maldonado, KA Terrani, BD Wirth Nuclear Engineering and Design 328, 10-26, 2018 | 27 | 2018 |
| Performance of U3Si2 in an LWR following a cladding breach during normal operation RT Sweet, Y Yang, KA Terrani, BD Wirth, AT Nelson Journal of Nuclear Materials 539, 152263, 2020 | 16 | 2020 |
| Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol I: PWR fuel R Hall, R Cumberland, R Sweet, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 13 | 2021 |
| Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends R Hall, R Sweet, R Belles, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 12 | 2021 |
| BISON fuel performance analysis of FeCrAl cladding with updated properties R Sweet, N George, K Terrani, B Wirth Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), p. Medium: ED, 2016 | 11 | 2016 |
| Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient N Capps, R Sweet, BD Wirth, A Nelson, K Terrani Nuclear Engineering and Design 366, 110744, 2020 | 10 | 2020 |
| High-burnup fuel stress analysis prior to and during a LOCA transient N Capps, R Sweet, J Harp, CM Petrie Journal of Nuclear Materials 556, 153194, 2021 | 9 | 2021 |
| Chromium-coated cladding analysis under simulated LOCA burst conditions R Sweet, P Mouche, S Bell, K Kane, N Capps Annals of Nuclear Energy 176, 109275, 2022 | 8 | 2022 |
| Metallic fuel performance benchmarks for versatile test reactor applications JA Hirschhorn, JJ Powers, I Greenquist, RT Sweet, J Hu, DL Porter, ... Nuclear Science and Engineering 196 (sup1), 123-147, 2022 | 7 | 2022 |
| Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications N Capps, R Sweet Journal of Nuclear Materials 563, 153621, 2022 | 7 | 2022 |
| Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives A Cheniour, RT Sweet, AT Nelson, BA Wilson, AE Shields Nuclear Engineering and Design 410, 112383, 2023 | 6 | 2023 |
| Advancements in modeling fuel pulverization and cladding behavior during a LOCA KA Gamble, LK Aagesen Jr, S Biswas, W Jiang, AM Recuero, JD Hales, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021 | 6 | 2021 |
| Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors NM George, RT Sweet, JJ Powers, A Worrall, KA Terrani, BD Wirth, ... Annals of Nuclear Energy 132, 486-503, 2019 | 6 | 2019 |
| Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding CP Massey, KA Kane, RT Sweet, SB Bell, SN Dryepondt, J Burns, ... Materials & Design 234, 112307, 2023 | 5 | 2023 |
| Model for determining rupture area in Zircaloy cladding under LOCA conditions N Capps, R Sweet Nuclear Engineering and Design 401, 112096, 2023 | 5 | 2023 |
| MARVEL Reactor Fuel Performance Report JA Evans, RT Sweet, DD Keiser Jr Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 3 | 2023 |
| Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel, Volume II: BWR RM Cumberland, RT Sweet, U Mertyurek, R Hall, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 3 | 2021 |
| Analysis of FeCrAl cladding and UO2 fuel including discrete and smeared cracks, and fuel relocation RT Sweet, BD Wirth, AT Nelson Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 3 | 2018 |
Brian D WirthGovernor's Chair Professor of Computational Nuclear Engineering, University of TennesseeVerified email at utk.edu
