| 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 |
| Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT R Hernandez, CP Folsom, NE Woolstenhulme, CB Jensen, JD Bess, ... Progress in Nuclear Energy 123, 103303, 2020 | 28 | 2020 |
| Deformation analysis of SiC-SiC channel box for BWR applications G Singh, J Gorton, D Schappel, NR Brown, Y Katoh, BD Wirth, KA Terrani Journal of Nuclear Materials 513, 71-85, 2019 | 24 | 2019 |
| Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR JP Gorton, BS Collins, AT Nelson, NR Brown Nuclear Engineering and Design 355, 110317, 2019 | 23 | 2019 |
| Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and … JP Gorton, SK Lee, Y Lee, NR Brown Nuclear Engineering and Design 353, 110295, 2019 | 20 | 2019 |
| Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor JP Gorton, NR Brown Nuclear Engineering and Design 370, 110865, 2020 | 13 | 2020 |
| Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety JP Gorton, D Schappel, AT Nelson, NR Brown Journal of Nuclear Materials 542, 152492, 2020 | 13 | 2020 |
| Pre-conceptual high temperature gas cooled microreactor design utilizing two-phase composite moderators. Part II: Design space and safety characteristics EM Duchnowski, V Karriem, K Skidmore, JP Gorton, LL Snead, ... Progress in Nuclear Energy 149, 104248, 2022 | 8 | 2022 |
| Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs G Singh, JP Gorton, D Schappel, BS Collins, Y Katoh, NR Brown, ... Nuclear Engineering and Design 363, 110621, 2020 | 8 | 2020 |
| Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor J McDuffee, R Christensen, D Eichel, M Simpson, S Phongikaroon, X Sun, ... Nuclear Science and Engineering 196 (sup1), 234-259, 2022 | 5 | 2022 |
| Assessment of CASL VERA for BWR analysis and application to accident tolerant SiC/SiC channel box JP Gorton, BS Collins, AJ Wysocki, NR Brown Nuclear Engineering and Design 365, 110732, 2020 | 5 | 2020 |
| A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification JP Gorton, CM Petrie, AT Nelson Progress in Nuclear Energy 162, 104737, 2023 | 2 | 2023 |
| Simulation of natural circulation cartridge loop experiments and application to molten salt reactors JP Gorton, DC Sweeney, CM Petrie, JL McDuffee Nuclear Engineering and Design 392, 111767, 2022 | 2 | 2022 |
| Status Report on Irradiation of MiniFuel Targets Bearing TRISO Fuel Compacts AG Le Coq, JP Gorton, ZG Wallen, TJ Gerczak, KD Linton Oak Ridge National Laboratory, ORNL/TM-2022/2456, 2022 | 2 | 2022 |
| A Demonstration of BWR Coupled Analysis and Potential ATF Applications Using CASL's MPACT/CTF JP Gorton, BS Collins, NR Brown Minneapolis, MN, 2019 | 2 | 2019 |
| Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation B Wirth, GP Singh, J Gorton, D Schappel, N Brown, Y Katoh, KA Terrani Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 2 | 2018 |
| Reactivity-initiated accidents in two pressurized water reactor high burnup core designs MA Fox, IO Lindsay, JP Gorton, NR Brown Nuclear Engineering and Design 415, 112745, 2023 | 1 | 2023 |
| Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification JP Gorton, RC Gallagher, ZG Wallen, AG Le Coq, GW Helmreich, ... Nuclear Engineering and Design 404, 112177, 2023 | 1 | 2023 |
| Thermal Optimization of UO2-Mo Fuel Using Sensitivity Analysis and Genetic Algorithms J Gorton, D Schappel, J McDuffee, C Petrie, A Nelson Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 1 | 2022 |
| Initial Design of High-Temperature MiniFuel Irradiation Experiments in the High Flux Isotope Reactor Removable Beryllium Region J Gorton, Z Wallen, C Petrie Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 1 | 2021 |
