Jeffrey J. Powers, Ph.D.
Affiliations: | 2011 | Nuclear Engineering | University of California, Berkeley, Berkeley, CA, United States |
Area:
Nuclear Engineering, Materials Science Engineering, EnergyGoogle:
"Jeffrey Powers"Parents
Sign in to add mentor| Ehud Greenspan | grad student | 2011 | UC Berkeley | |
| (TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket.) | ||||
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Publications
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| Stimpson S, Clarno K, Pawlowski R, et al. (2020) Coupled fuel performance calculations in VERA and demonstration on Watts Bar unit 1, cycle 1 Annals of Nuclear Energy. 145: 107554 |
| George NM, Sweet RT, Powers JJ, et al. (2019) Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors Annals of Nuclear Energy. 132: 486-503 |
| Wooten D, Powers JJ. (2018) A Review of Molten Salt Reactor Kinetics Models Nuclear Science and Engineering. 191: 203-230 |
| Schappel D, Terrani K, Powers J, et al. (2018) Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON Nuclear Engineering and Design. 335: 116-127 |
| Stimpson S, Powers J, Clarno K, et al. (2018) Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 Nuclear Engineering and Design. 327: 172-186 |
| Losa E, Košťál M, Czakoj T, et al. (2018) Neutronic experiments with fluorine rich compounds at LR-0 reactor Annals of Nuclear Energy. 120: 286-295 |
| Powers JJ, Brown NR, Mueller DE, et al. (2018) Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors Annals of Nuclear Energy. 120: 319-332 |
| Betzler BR, Robertson S, Davidson EE, et al. (2018) Fuel cycle and neutronic performance of a spectral shift molten salt reactor design Annals of Nuclear Energy. 119: 396-410 |
| Petti D, Hill R, Gehin J, et al. (2017) A Summary of the Department of Energy’s Advanced Demonstration and Test Reactor Options Study Nuclear Technology. 199: 111-128 |
| Betzler BR, Powers JJ, Worrall A. (2017) Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE Annals of Nuclear Energy. 101: 489-503 |