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Garry S. Holman

Observed names: G Holman, G S Holman, G. Holman, G.S. Holman, Holman, Garry S., Holman, Garry S. author.
OpenAlex ID: A5065377164
Probability of pipe failure in the reactor coolant loops of Combustion Engineering PWR plants. Volume 2. Pipe failure induced by crack growth
1984 · T. Lo, R. Mensing, et al. · 9
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Power-cooling mismatch test series. Test PCM-2A; test results report. [PWR]
1976 · G. Cawood, G. Holman, et al. · 4
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Double-ended breaks in reactor primary piping
1985 · Garry S. Holman · Nuclear Engineering and Design · 3
Reactor options for disposition of excess weapon plutonium: Selection criteria and decision process for assessment
1994 · Lawrence Livermore National Lab., CA (United States), T Edmunds, et al. · 2
Component fragility research program
1989 · Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering, N Tsai, et al. · 2
Probability of failure in BWR reactor coolant piping: Volume 1, Summary report
1989 · G. Holman, C. Chou · 2
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Component Fragility Research Program: Phase 1 component prioritization
1987 · G.S. Holman, C.K. Chou · 2
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Failure probability of PWR reactor coolant loop piping. [Double-ended guillotine break]
1984 · T. Lo, H.H. Woo, et al. · 2
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Probabilistic cost-benefit analysis of enhanced safety features for strategic nuclear weapons at a representative location
1993 · D.R. Stephens, C.H. Hall, et al. · University of North Texas Digital Library (University of North Texas) · 1
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Application of reliability techniques to prioritize BWR (boiling water reactor) recirculation loop welds for in-service inspection
1989 · Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering, G. Holman, et al. · 1
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Component Fragility Research Program: Phase 1, Demonstration tests: Volume 1, Summary report
1987 · G.S. Holman, C.K. Chou, et al. · 1
Probability of pipe failure in the reactor coolant loops of Combustion Engineering PWR plants. Volume 1. Summary report
1985 · G. Holman, T. Lo, et al. · 1
Performance Analysis: Issues Tracking System Data through June 2013
2014 · C. Kerr, USDOE, et al.
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Performance Analysis: Issues Tracking System Data through June 2012
2013 · C. Kerr, USDOE, et al.
Performance Analysis: Issues Tracking System Data through September 2011
2012 · C. Kerr, USDOE, et al.
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PC-PRAISE. Piping Reliability Analysis Including Seismic Events
1992 · Shaowu Lu, G.S. Holman, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Probability of crack-induced failure in BWR recirculation piping
1989 · Garry S. Holman · Nuclear Engineering and Design
Probability of failure in BWR (Boiling Water Reactor) reactor coolant piping: Volume 2, Pipe failure induced by crack growth and failure of intermediate supports
1989 · T. Lo, S. Bumpus, et al.
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Using Reliability Techniques to Investigate Pipe Breaks Caused by Seismically-Induced Support Failures
1989 · Ting-Yu Lo, G.S. Holman · NCSU Libraries Repository (North Carolina State University Libraries)
Component Fragility Research Program: Phase 1, Demonstration tests: Volume 2, Appendices
1987 · G.S. Holman, C.K. Chou, et al.
Probability of pipe failure in the reactor coolant loops of Babcock and Wilcox PWR plants. Volume 1. Summary report
1986 · G.S. Holman, C.K. Chou · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Probability of pipe failure in the reactor coolant loops of Westinghouse PWR Plants. Volume 1. Summary report
1985 · G. Holman, C. Chou
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Probability of pipe failure in the reactor coolant loops of Westinghouse PWR plants. Volume 4. Pipe failure induced by crack growth in west coast plants
1985 · D. Chinn, G. Holman, et al.
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Assessment of value-impact associated with the elimination of postulated pipe ruptures from the design basis for nuclear power plants
1985 · G.S. Holman, C.K. Chou
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Equipment fragility testing
1985 · G.S. Holman, C.K. Chou, et al. · University of North Texas Digital Library (University of North Texas)
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Works count: 49
Citation count: 30
H-index: 3
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