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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.
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  • Author HeadingSTEPHENS, D.R. HALL, C.H. HOLMAN, G.S. GRAHAM, K.F. HARVEY, T.F. SER...

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.
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  • Author HeadingNG, D.S. HOLMAN, G.S.

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.
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  • Author HeadingHOLMAN, G.S.

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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  • Author HeadingHOLMAN, G.S.

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.
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  • Author HeadingHOLMAN, G.S.

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.
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  • Author HeadingHOLMAN, G.S.

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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  • Author HeadingHolman, G.S. Chou, C.K.

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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  • Author HeadingHOLMAN, G.S.

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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  • Author HeadingHolman, G.S. Chou, C.K. Shipway, G.D. Gloz...

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.
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  • Author HeadingHOLMAN, G.S.

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.
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  • Author HeadingChou, C.K. Glozman, V. Holman, G.S. Shipway, G.D.

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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  • Author HeadingHolman, G.S. Chou, C.K.

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.
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  • Author HeadingHOLMAN, G.S.

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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  • Author HeadingHOLMAN, G.S.

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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  • Author HeadingHolman, G.S. Chou, C.K.

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.
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  • Author HeadingChou, C.K. Holman, G.S. Lo, T.

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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  • Author HeadingHOLMAN, G.S.

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

EQUIPMENT FRAGILITY TESTING (CONF ; CONF-850809--30)
Paper図書
1985.
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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.
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  • Author HeadingHOLMAN, G.S.
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