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PROBABILISTIC COST-BENEFIT ANALYSIS OF ENHANCED SAFETY FEATURES FOR STRATEGIC NUCLEAR WEAPONS AT A REPRESENTATIVE LOCATION (UCRL ; UCRL-JC-115269)

PROBABILISTIC COST-BENEFIT ANALYSIS OF ENHANCED SAFETY FEATURES FOR STRATEGIC NUCLEAR WEAPONS AT A REPRESENTATIVE LOCATION (UCRL ; UCRL-JC-115269)
Paper図書
STEPHENS, D.R.// HALL, C.H.// HOLMAN, G.S.// GRAHAM, K.F.// HARVEY, T.F.// SERDUKE, F.J.D. (LAWRENCE LIVERMORE NATIONAL LAB., CA (UNITED STATES))University of California Research Laboratory(University of California Research Laboratory)1993.
Other Libraries in Japan

WIND/TORNADO GUIDELINES STUDY (UCRL ; UCRL-JC-108907)

WIND/TORNADO GUIDELINES STUDY (UCRL ; UCRL-JC-108907)
Paper図書
NG, D.S.// HOLMAN, G.S. (LAWRENCE LIVERMORE NATIONAL LAB., CA (UNITED STATES))University of California Research Laboratory(University of California Research Laboratory)1991.
Other Libraries in Japan

PROBABILITY OF FAILURE IN BWR REACTOR COOLANT PIPING: VOLUME 1, SUMMARY REPORT. (NUREG ; NUREG-CR-4792-VOL.1)

PROBABILITY OF FAILURE IN BWR REACTOR COOLANT PIPING: VOLUME 1, SUMMARY REPORT. (NUREG ; NUREG-CR-4792-VOL.1)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
Other Libraries in Japan

APPLICATION OF RELIABILITY TECHNIQUES TO PRIORITIZE BWR (BOILING WATER REACTOR) RECIRCULATION LOOP WELDS FOR IN-SERVICE INSPECTION. (NUREG ; NUREG/CR-5486)

APPLICATION OF RELIABILITY TECHNIQUES TO PRIORITIZE BWR (BOILING WATER REACTOR) RECIRCULATION LOOP WELDS FOR IN-SERVICE INSPECTION. (NUREG ; NUREG/CR-5486)
Paper図書
HOLMAN, G.S.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
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COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1 DEMONSTRATION TESTS. VOLUME 1, SUMMARY REPORT. (TECHNICAL REPT.) (NUREG ; NUREG-CR-4900-V1; UCID-21002-VOL-1)

COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1 DEMONSTRATION TESTS. VOLUME 1, SUMMARY REPORT. (TECHNICAL REPT.) (NUREG ; NUREG-CR-4900-V1; UCID-21002-VOL-1)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan

COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1, DEMONSTRATION TESTS: VOLUME 1, SUMMARY REPORT. (NUREG ; NUREG-CR-4900-VOL.1)

COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1, DEMONSTRATION TESTS: VOLUME 1, SUMMARY REPORT. (NUREG ; NUREG-CR-4900-VOL.1)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
Other Libraries in Japan

Component Fragility Research Program: Phase 1 component prioritization (NUREG ; NUREG/CR-4899)

Component Fragility Research Program: Phase 1 component prioritization (NUREG ; NUREG/CR-4899)
Paper図書
Holman, G.S., Chou, C.K.Lawrence Livermore National Lab.1987.6.
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COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1 DEMONSTRATION TESTS. VOLUME 2 APPENDICES. (TECHNICAL REPT.) (NUREG ; NUREG-CR-4900-V2; UCID-21002-VOL-2)

COMPONENT FRAGILITY RESEARCH PROGRAM: PHASE 1 DEMONSTRATION TESTS. VOLUME 2 APPENDICES. (TECHNICAL REPT.) (NUREG ; NUREG-CR-4900-V2; UCID-21002-VOL-2)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
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Component Fragility Research Program: Phase 1, Demonstration tests: Volume 2, Appendices (NUREG ; NUREG/CR-4900-Vol.2; UCID-21002-Vol.2; TI87014129)

Component Fragility Research Program: Phase 1, Demonstration tests: Volume 2, Appendices (NUREG ; NUREG/CR-4900-Vol.2; UCID-21002-Vol.2; TI87014129)
Paper図書
Holman, G.S. [et al.]Lawrence Livermore National Lab.1987.8.
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PROBABILITY OF PIPE FAILURE IN THE REACTOR COOLANT LOOPS OF BABCOCK AND WILCOX PWR PLANTS. VOLUME 1. SUMMARY REPORT. (NUREG ; NUREG-CR-4290-VOL.1)

PROBABILITY OF PIPE FAILURE IN THE REACTOR COOLANT LOOPS OF BABCOCK AND WILCOX PWR PLANTS. VOLUME 1. SUMMARY REPORT. (NUREG ; NUREG-CR-4290-VOL.1)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
Other Libraries in Japan

Component Fragility Research Program: Phase 1, Demonstration tests: Volume 1, Summary report (UCID ; UCID-21002-VOL.1)

Component Fragility Research Program: Phase 1, Demonstration tests: Volume 1, Summary report (UCID ; UCID-21002-VOL.1)
Paper図書
Lawrence Livermore National Lab., CA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering(Lawrence Livermore National Lab., CA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering)1987.
Other Libraries in Japan

Probability of pipe failure in the reactor coolant loops of Westinghouse PWR Plants. Volume 1. Summary report (NUREG ; NUREG/CR-3660-Vol.1)

Probability of pipe failure in the reactor coolant loops of Westinghouse PWR Plants. Volume 1. Summary report (NUREG ; NUREG/CR-3660-Vol.1)
Paper図書
Holman, G.S., Chou, C.K.Lawrence Livermore National Lab.1985.7.
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PROBABILITY OF PIPE FAILURE IN THE REACTOR COOLANT LOOPS OF COMBUSTION ENGINEERING PWR PLANTS. VOLUME 1. (NUREG ; NUREG-CR-3663-VOL.1)

PROBABILITY OF PIPE FAILURE IN THE REACTOR COOLANT LOOPS OF COMBUSTION ENGINEERING PWR PLANTS. VOLUME 1. (NUREG ; NUREG-CR-3663-VOL.1)
Paper図書
HOLMAN, G.S.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan

EQUIPMENT FRAGILITY TESTING. (UCRL ; UCRL-92303)

EQUIPMENT FRAGILITY TESTING. (UCRL ; UCRL-92303)
Paper図書
HOLMAN, G.S.(et al.)California Univ., Livermore (USA). Lawrence Livermore Lab(California Univ., Livermore (USA). Lawrence Livermore Lab)1985.
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Assessment of value-impact associated with the elimination of postulated pipe ruptures from the design basis for nuclear power plants (UCID ; UCID-20397; TI85010404)

Assessment of value-impact associated with the elimination of postulated pipe ruptures from the design basis for nuclear power plants (UCID ; UCID-20397; TI85010404)
Paper図書
Holman, G.S., Chou, C.K.Lawrence Livermore National Lab.1985.3.29.
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Probability of pipe failure in the reactor coolant loops of Combustion Engineering PWR plants. Volume 1. Summary report (UCRL ; UCRL-53500-VOL.1)

Probability of pipe failure in the reactor coolant loops of Combustion Engineering PWR plants. Volume 1. Summary report (UCRL ; UCRL-53500-VOL.1)
Paper図書
University of California Research Laboratory(University of California Research Laboratory)1985.
Other Libraries in Japan

PROBABILISTIC ANALYSES OF FAILURE IN REACTOR COOLANT PIPING. (UCRL ; UCRL-91292)

PROBABILISTIC ANALYSES OF FAILURE IN REACTOR COOLANT PIPING. (UCRL ; UCRL-91292)
Paper図書
HOLMAN, G.S.California Univ., Livermore (USA). Lawrence Livermore Lab(California Univ., Livermore (USA). Lawrence Livermore Lab)1984.
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PROBABILISTIC ANALYSES OF FAILURE IN REACTOR COOLANT PIPING. [DOUBLE-ENDED GUILLOTINE BREAK] (CONF ; CONF-840763-4)

PROBABILISTIC ANALYSES OF FAILURE IN REACTOR COOLANT PIPING. [DOUBLE-ENDED GUILLOTINE BREAK] (CONF ; CONF-840763-4)
Paper図書
1984.
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  • Author HeadingHolman, G S

EQUIPMENT FRAGILITY TESTING (CONF ; CONF-850809--30)

EQUIPMENT FRAGILITY TESTING (CONF ; CONF-850809--30)
Paper図書
1985.
Other Libraries in Japan
  • Author HeadingHolman, G S Chou, C K Cummings, G E

DOUBLED-ENDED BREAKS IN REACTOR PRIMARY PIPING. (UCRL ; UCRL-91731)

DOUBLED-ENDED BREAKS IN REACTOR PRIMARY PIPING. (UCRL ; UCRL-91731)
Paper図書
HOLMAN, G.S.California Univ., Livermore (USA). Lawrence Livermore Lab(California Univ., Livermore (USA). Lawrence Livermore Lab)1984.
Other Libraries in Japan
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