Παρακολούθηση
Jeffrey J Powers
Jeffrey J Powers
Η διεύθυνση ηλεκτρονικού ταχυδρομείου έχει επαληθευτεί στον τομέα ornl.gov
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Παρατίθεται από
Παρατίθεται από
Έτος
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
2632015
A review of TRISO fuel performance models
JJ Powers, BD Wirth
Journal of Nuclear Materials 405 (1), 74-82, 2010
2542010
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
1022017
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
692013
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
692009
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
572016
Liquid fuel molten salt reactors for thorium utilization
JC Gehin, JJ Powers
Nuclear Technology 194 (2), 152-161, 2016
532016
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
482017
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
452018
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
452017
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
452017
Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts
NM George, KA Terrani, JJ Powers
ORNL/TM-2013 121, 2013
402013
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
392015
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
382018
A review of molten salt reactor kinetics models
D Wooten, JJ Powers
Nuclear Science and Engineering 191 (3), 203-230, 2018
372018
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
352009
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
332014
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
332013
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
312018
Molten salt reactor experiment benchmark evaluation
M Fratoni, D Shen, G Ilas, J Powers
Univ. of California, Berkeley, CA (United States); Oak Ridge National Lab …, 2020
302020
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