| Screening of advanced cladding materials and UN–U 3 Si 5 fuel NR Brown, M Todosow, A Cuadra Journal of Nuclear Materials 462, 26-42, 2015 | 91 | 2015 |
| Neutronic performance of uranium nitride composite fuels in a PWR NR Brown, A Aronson, M Todosow, R Brito, KJ McClellan Nuclear Engineering and Design 275, 393-407, 2014 | 85 | 2014 |
| Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients NR Brown, H Ludewig, A Aronson, G Raitses, M Todosow Annals of Nuclear Energy 62, 538-547, 2013 | 74 | 2013 |
| Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback NR Brown, H Ludewig, A Aronson, G Raitses, M Todosow Annals of Nuclear Energy 62, 548-557, 2013 | 67 | 2013 |
| Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel SK Lee, M Liu, NR Brown, KA Terrani, ED Blandford, H Ban, CB Jensen, ... International Journal of Heat and Mass Transfer 132, 643-654, 2019 | 60 | 2019 |
| A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications NR Brown Journal of Nuclear Materials 534, 152139, 2020 | 58 | 2020 |
| Micro heat pipe nuclear reactor concepts: Analysis of fuel cycle performance and environmental impacts R Hernandez, M Todosow, NR Brown Annals of Nuclear Energy 126, 419-426, 2019 | 54 | 2019 |
| The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors NR Brown, AJ Wysocki, KA Terrani, KG Xu, DM Wachs Annals of Nuclear Energy 99, 353-365, 2017 | 52 | 2017 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis NR Brown, BR Betzler, JJ Carbajo, AJ Wysocki, MS Greenwood, C Gentry, ... Annals of Nuclear Energy 103, 49-59, 2017 | 50 | 2017 |
| A review of catalytic sulfur (VI) oxide decomposition experiments NR Brown, ST Revankar international journal of hydrogen energy 37 (3), 2685-2698, 2012 | 50 | 2012 |
| Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics C Lu, BD Hiscox, KA Terrani, NR Brown Annals of Nuclear Energy 114, 277-287, 2018 | 49 | 2018 |
| 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 |
| Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys AF Ali, JP Gorton, NR Brown, KA Terrani, CB Jensen, Y Lee, ... Nuclear Engineering and Design 338, 218-231, 2018 | 47 | 2018 |
| Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5% JR Burns, R Hernandez, KA Terrani, AT Nelson, NR Brown Annals of Nuclear Energy 142, 107423, 2020 | 42 | 2020 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview AL Qualls, BR Betzler, NR Brown, JJ Carbajo, MS Greenwood, R Hale, ... Annals of Nuclear Energy 107, 144-155, 2017 | 40 | 2017 |
| Advanced Demonstration and Test Reactor Options Study DA Petti, R Hill, J Gehin, HD Gougar, G Strydom, F Heidet, J Kinsey, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2017 | 40 | 2017 |
| Advanced demonstration and test reactor options study DA Petti, R Hill, J Gehin, HD Gougar, G Strydom, F Heidet, J Kinsey, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2017 | 40 | 2017 |
| Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents M Liu, NR Brown, KA Terrani, AF Ali, ED Blandford, DM Wachs Annals of Nuclear Energy 110, 48-62, 2017 | 39 | 2017 |
| 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 | 35 | 2021 |
| Candidate core designs for the transformational Challenge reactor BJ Ade, BR Betzler, AJ Wysocki, MS Greenwood, PC Chesser, KA Terrani, ... Journal of Nuclear Engineering 2 (1), 74-85, 2021 | 35 | 2021 |
