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Robert F. Kile
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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
362021
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
222020
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
182022
Power Level Downselection for the Transformational Challenge Reactor
BR Betzler, BJ Ade, A Wysocki, PK Jain, MS Greenwood, JD Rader, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
122020
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
102022
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
92022
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
82021
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
62022
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
42022
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
32023
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
22019
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
12022
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
12022
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
12020
RELAP5-3D validation studies based on the High Temperature Test facility
RF Kile, AS Epiney, NR Brown
Nuclear Engineering and Design 426, 113401, 2024
2024
OECD-NEA HTTF Benchmark Progress and Updates
RF Kile
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023
2023
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
2023
Assessment of Modeling Capabilities and Transient Performance for High-Temperature Reactors
RF Kile
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
2022
Assessing the Impact of Effective Thermal Conductivity on Gas-cooled Reactor Transients in RELAP5-3D
RF Kile, AS Epiney, NR Brown
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2022
2022
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