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W.L. Ferrell

Observed name: W. Ferrell
OpenAlex ID: A5112019331
On the safety of Tokamak-type, central station fusion power reactors
1976 · D. Okrent, W.E. Kastenberg, et al. · Nuclear Engineering and Design · 24
Analysis of core damage frequency from internal events: Peach Bottom, Unit 2
1986 · A.M. Kolaczkowski, J.A. Lambright, et al. · 13
Some Safety Studies for Conceptual Fusion–Fission Hybrid Reactors (Final Report)
1978 · Univ. of California, Los Angeles, CA (United States), William Kastenberg, et al. · 1
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Developments in Online Monitoring Technologies for Autonomous Microreactor Operations
2021 · A. Hashemian, B. Shumaker, et al. · Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT)
Validation of VERA Software for Nuclear Power Plant Life Extension Applications
2021 · J. Houser, S. Tyler, et al. · Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT)
Value impact assessment of standard review plan sections
1981 · A.M. Kolaczkowski, Alexander García-Aristizábal, et al. · University of North Texas Digital Library (University of North Texas)
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Some safety aspects of Tokamak-type fusion power reactors
1979 · W.L. Ferrell
Loss-of-coolant accidents in lithium-cooled fusion blankets
1977 · W.L. Ferrell, Candace K. Chan, et al. · Transactions of the American Nuclear Society
Nonlinear temperature-density stability in tokamak reactors operating on the D-T cycle
1976 · W.L. Ferrell, W.E. Kastenberg
Analysis of loss-of-flow accidents in lithium-cooled CTR devices
1975 · T.E. Botts, W.L. Ferrell, et al. · Transactions of the American Nuclear Society
Safety analysis of some tokamak-type fusion power reactor concepts
1975 · W.E. Kastenberg, D. Okrent, et al. · Transactions of the American Nuclear Society
Works count: 11
Citation count: 38
H-index: 2
I10-index: 2
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