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AbstractAbstract
[en] This paper deals with the limitation and its further development of Seismic PSA (probabilistic safety assessment) in the view point of human error in structural design and construction process, and also logical failure of safety-related computers, instrumentation systems, logical mechanics such as pilot-operated safety valves under seismic events. Shibata, one of the authors, has been collecting the data on damages of industrial facilities due to past destructive earthquakes since 1964, and he concluded that both logical problems were also significant factors for Seismic PSA as well as the factors which had been discussed such as local seismicity, response fluctuation, and fragility curve. The authors recognized this fact through the cooperative study on Seismic PSA as an activity of the Subcommittee on Seismic Risk Study, to which the authors belong, in the Japan Atomic Energy Research Institute (JAERI). This paper consists of three parts. The first part deals with the summary of the JAERI's work and their issues. The second and third parts deal with human error which will be expected in structural design process and logical failure of logical systems
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Source
Molina, T. (ed.); Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (United States); 475 p; Feb 1991; p. 167-175; Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations; Santa Fe, NM (United States); 4-6 Sep 1990; SAND--90-2797; CONF-9009346--; OSTI as TI91008351; NTIS; INIS
Record Type
Report
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Conference
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AFTER-HEAT REMOVAL, BWR TYPE REACTORS, CONSTRUCTION, CONTAINMENT SYSTEMS, CORIUM, EARTHQUAKES, FAILURE MODE ANALYSIS, FAILURES, FAULT TREE ANALYSIS, HUMAN FACTORS, JAERI, LOSS OF COOLANT, MECHANICAL STRUCTURES, MELTDOWN, OUTAGES, PROBABILISTIC ESTIMATION, PWR TYPE REACTORS, REACTOR CORE DISRUPTION, REACTOR INSTRUMENTATION, REACTOR SAFETY, RELIABILITY, RESEARCH PROGRAMS, RISK ASSESSMENT, SAFETY ENGINEERING, SEISMIC EFFECTS, SENSITIVITY ANALYSIS, SPECIFICATIONS, VALVES
ACCIDENTS, CONTAINMENT, CONTROL EQUIPMENT, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, JAPANESE ORGANIZATIONS, NATIONAL ORGANIZATIONS, POWER REACTORS, REACTOR ACCIDENTS, REACTORS, REMOVAL, SAFETY, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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