| Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors NM George, K Terrani, J Powers, A Worrall, I Maldonado Annals of Nuclear Energy 75, 703-712, 2015 | 250 | 2015 |
| A review of TRISO fuel performance models JJ Powers, BD Wirth Journal of Nuclear Materials 405 (1), 74-82, 2010 | 230 | 2010 |
| Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE BR Betzler, JJ Powers, A Worrall Annals of Nuclear Energy 101, 489-503, 2017 | 98 | 2017 |
| Neutron transport and nuclear burnup analysis for the laser inertial confinement fusion-fission energy (LIFE) engine KJ Kramer, JF Latkowski, RP Abbott, JK Boyd, JJ Powers, JE Seifried Fusion Science and Technology 56 (2), 625-631, 2009 | 67 | 2009 |
| Fully ceramic microencapsulated (FCM) replacement fuel for LWRs JJ Powers, WJ Lee, F Venneri, LL Snead, CK Jo, DH Hwang, JH Chun, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2013 | 64 | 2013 |
| 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 | 54 | 2016 |
| Liquid fuel molten salt reactors for thorium utilization JC Gehin, JJ Powers Nuclear Technology 194 (2), 152-161, 2016 | 49 | 2016 |
| 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 | 43 | 2017 |
| 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 | 42 | 2017 |
| Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON D Schappel, K Terrani, JJ Powers, LL Snead, BD Wirth Nuclear Engineering and Design 335, 116-127, 2018 | 41 | 2018 |
| 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 | 39 | 2017 |
| Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts NM George, KA Terrani, JJ Powers ORNL/TM-2013 121, 2013 | 39 | 2013 |
| Fuel cycle and neutronic performance of a spectral shift molten salt reactor design BR Betzler, S Robertson, EE Davidson, JJ Powers, A Worrall, L Dewan, ... Annals of Nuclear Energy 119, 396-410, 2018 | 38 | 2018 |
| 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 | 38 | 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 |
| Molten salt fuel version of laser inertial fusion fission energy (LIFE) RW Moir, HF Shaw, A Caro, L Kaufman, JF Latkowski, J Powers, ... Fusion Science and Technology 56 (2), 632-640, 2009 | 33 | 2009 |
| Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors NM George, I Maldonado, K Terrani, A Godfrey, J Gehin, J Powers Nuclear Technology 188 (3), 238-251, 2014 | 32 | 2014 |
| Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 S Stimpson, J Powers, K Clarno, R Pawlowski, R Gardner, S Novascone, ... Nuclear Engineering and Design 327, 172-186, 2018 | 31 | 2018 |
| A review of molten salt reactor kinetics models D Wooten, JJ Powers Nuclear Science and Engineering 191 (3), 203-230, 2018 | 30 | 2018 |
| Standardized verification of fuel cycle modeling B Feng, B Dixon, E Sunny, A Cuadra, J Jacobson, NR Brown, J Powers, ... Annals of Nuclear Energy 94, 300-312, 2016 | 30 | 2016 |
Andrew WorrallOak Ridge National Laboratory在 ornl.gov 的电子邮件经过验证
