| Accident tolerant fuels for LWRs: A perspective SJ Zinkle, KA Terrani, JC Gehin, LJ Ott, LL Snead Journal of Nuclear Materials 448 (1-3), 374-379, 2014 | 1074 | 2014 |
| Microencapsulated fuel technology for commercial light water and advanced reactor application KA Terrani, LL Snead, JC Gehin Journal of Nuclear Materials 427 (1-3), 209-224, 2012 | 263 | 2012 |
| Pre-conceptual design of a fluoride-salt-cooled small modular advanced high-temperature reactor (SmAHTR) SR Greene, JC Gehin, DE Holcomb, JJ Carbajo, D Ilas, AT Cisneros, ... Oak Ridge National Laboratory, ORNL/TM-2010/199, 2010 | 143 | 2010 |
| VERA core simulator methodology for pressurized water reactor cycle depletion B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ... Nuclear Science and Engineering 185 (1), 217-231, 2017 | 121 | 2017 |
| Nuclear fuel cycle evaluation and screening–final report R Wigeland, T Taiwo, H Ludewig, M Todosow, W Halsey, J Gehin, ... US Department of Energy, 51, 2014 | 111 | 2014 |
| Fast spectrum molten salt reactor options DE Holcomb, GF Flanagan, BW Patton, JC Gehin, RL Howard, ... ORNL/TM-2011/105, 2011 | 91 | 2011 |
| A quasi-static polynomial nodal method for nuclear reactor analysis JC Gehin Oak Ridge Inst. for Science and Education, TN (United States); Massachusetts …, 1992 | 83 | 1992 |
| Study of Fukushima Daiichi nuclear power station unit 4 spent-fuel pool D Wang, IC Gauld, GL Yoder, LJ Ott, GF Flanagan, MW Francis, EL Popov, ... Nuclear technology 180 (2), 205-215, 2012 | 75 | 2012 |
| Core and refueling design studies for the advanced high temperature reactor DE Holcomb, D Ilas, VK Varma, AT Cisneros, RP Kelly, JC Gehin ORNL/TM-2011/365, Oak Ridge National Laboratory, Oak Ridge, TN, 2011 | 57 | 2011 |
| VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12 A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ... Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016 | 56 | 2016 |
| Liquid fuel molten salt reactors for thorium utilization JC Gehin, JJ Powers Nuclear Technology 194 (2), 152-161, 2016 | 48 | 2016 |
| 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 |
| Next generation nuclear plant phenomena identification and ranking tables (PIRTs) volume 2: Accident and thermal fluids analysis PIRTs SJ Ball, M Corradini, SE Fisher, R Gauntt, G Geffraye, JC Gehin, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2008 | 40* | 2008 |
| Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems NR Brown, JJ Powers, B Feng, F Heidet, NE Stauff, G Zhang, M Todosow, ... Nuclear Engineering and design 289, 252-265, 2015 | 36 | 2015 |
| A summary of the Department of Energy’s advanced demonstration and test reactor options study D Petti, R Hill, J Gehin, H Gougar, G Strydom, T O’Connor, F Heidet, ... Nuclear Technology 199 (2), 111-128, 2017 | 35 | 2017 |
| Nuclear fuel cycle evaluation and screening R Wigeland, T Taiwo, H Ludewig, M Todosow, W Halsey, J Gehin Final Report, Fuel Cycle Research & Development FCRD-FCO-2014-000106 …, 2014 | 35 | 2014 |
| Assumptions and Criteria for Performing a Feasability Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel RT Primm Iii, RJ Ellis, JC Gehin, DL Moses, JL Binder, N Xoubi Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2006 | 35 | 2006 |
| VERA core simulator methodology for PWR cycle depletion B Kochunas, BS Collins, D Jabaay, KS Kim, A Graham, S Stimpson, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Oak Ridge …, 2015 | 33 | 2015 |
| A new approach for modeling and analysis of molten salt reactors using SCALE JJ Powers, TJ Harrison, JC Gehin International Conference on Mathematics and Computational Methods Applied to …, 2013 | 33 | 2013 |
Kurt TerraniUSNCE-mail megerősítve itt: usnc.com
