| 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 | 38 | 2021 |
| Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors EM Duchnowski, RF Kile, LL Snead, JR Trelewicz, NR Brown Nuclear Engineering and Design 368, 110824, 2020 | 24 | 2020 |
| SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis R Bostelmann, C Celik, RF Kile, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 22 | 2022 |
| Pre-conceptual high temperature gas-cooled microreactor design utilizing two-phase composite moderators. Part I: Microreactor design and reactor performance EM Duchnowski, RF Kile, K Bott, LL Snead, JR Trelewicz, NR Brown Progress in Nuclear Energy 149, 104257, 2022 | 16 | 2022 |
| Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor RF Kile, F Bostelmann, SE Skutnik, WA Wieselquist, NR Brown Annals of Nuclear Energy 173, 109107, 2022 | 14 | 2022 |
| Power level downselection for the transformational challenge reactor B Betzler, B Ade, A Wysocki, P Jain, S Greenwood, J Rader, J Heineman, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 12 | 2020 |
| TRISO SiC failure probability for reactivity initiated accidents in high-temperature gas-cooled reactors CG Ghezzi, RF Kile, NR Brown Nuclear Science and Engineering 196 (11), 1361-1382, 2022 | 11 | 2022 |
| Transformational challenge reactor analysis to inform preconceptual core design decisions: Sensitivity study of transient analysis in a hydride-moderated microreactor RF Kile, AJ Wysocki, BR Betzler, NR Brown Nuclear Engineering and Design 376, 111122, 2021 | 10 | 2021 |
| Overview of HTTF Modeling and Benchmark Efforts for Code Validation for Gas-Cooled Reactor Applications A Epiney, G Strydom, R Kile, MT Retamales, S Yoon, C Mueller, ... Proc. 4th Int. Conf. Generation IV Small Reactors (G4SR-4), 3-6, 2022 | 9 | 2022 |
| High Temperature Test Facility sensitivity and calibration studies to inform OECD-NEA benchmark calculations RF Kile, AS Epiney, NR Brown Nuclear Engineering and Design 404, 112178, 2023 | 6 | 2023 |
| RELAP5-3D validation studies based on the High Temperature Test facility RF Kile, AS Epiney, NR Brown Nuclear Engineering and Design 426, 113401, 2024 | 2 | 2024 |
| Code Benchmark of Pressurized Conduction Cooldown Transient in the High Temperature Test Facility T Hua, R Kile, SN Lee, L Zou, A Epiney 2024 International Congress on Advances in Nuclear Power Plants (ICAPP), 2024 | 2 | 2024 |
| Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis W Wieselquist, R Bostelmann, R Kile, A Lo, U Mertyurek, A Shaw, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 2 | 2022 |
| Initial development of a generic fluoride salt-cooled reactor model R Kile, R Bostelmann, S Skutnik, W Wieselquist, N Brown Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 2 | 2022 |
| Characteristics of Fuel Articles for Irradiation Testing in INL-TREAT and MIT-NRL G Vasudevamurthy, NR Brown, RF Kile, DP Schappel, KD Linton Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 2 | 2019 |
| Development of an Improved RELAP5-3D Model for the High Temperature Test Facility RF Kile, AS Epiney Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2024 | 1 | 2024 |
| RELAP5-3D Solutions to Exercise 1 of the OECD-NEA HTTF Benchmark RF Kile, AS Epiney, NR Brown Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 1 | 2023 |
| OECD/NEA High Temperature Test Facility (HTTF) Thermal-Hydraulics Benchmark: Proposed Exercises RF Kile, AS Epiney, NR Brown Transactions of the American Nuclear Society, Vol 127 (2022), 2022 | 1 | 2022 |
| Pre-conceptual design of a gas-cooled microreactor with two-phase composite moderators EM Duchnowski, RF Kile, JP Gorton, NR Brown Transactions of the American Nuclear Society 124 (1), 528-529, 2021 | 1 | 2021 |
| Informing Transient Testing of Fuel Designs for the Transformational Challenge Reactor★ R Kile, D Schappel, AJ Wysocki, G Vasudevamurthy, KA Terrani, ... Transactions of the American Nuclear Society 122, 236-238, 2020 | 1 | 2020 |
