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AbstractAbstract
[en] The success of probabilistic risk assessment (PRA) has led to numerous improvements to the safety of commercial nuclear power plants. Those very successes, however, have led to a situation where the events that PRAs have traditionally modeled are extremely rare. As a result, current PRAs have the potential to be misleading because events previously considered to be unimportant and, thus, not included in the scope of the analyses may now be dominant. This paper provides an assessment of the current status of accident sequence analysis methods and identifies particular limitations that should be addressed in future studies
Primary Subject
Secondary Subject
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. 221-230; 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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Country of publication
BWR TYPE REACTORS, CONSTRUCTION, CONTAINMENT SYSTEMS, FAILURES, HUMAN FACTORS, INFORMATION NEEDS, PRIMARY COOLANT CIRCUITS, PROBABILISTIC ESTIMATION, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR CORE DISRUPTION, REACTOR MAINTENANCE, REACTOR OPERATION, REACTOR SAFETY, REACTOR SHUTDOWN, RESEARCH PROGRAMS, RISK ASSESSMENT, SAFETY ENGINEERING, SANDIA LABORATORIES, SPECIFICATIONS, US DOE, US NRC
ACCIDENTS, CONTAINMENT, COOLING SYSTEMS, ENRICHED URANIUM REACTORS, MAINTENANCE, NATIONAL ORGANIZATIONS, OPERATION, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SAFETY, SANDIA NATIONAL LABORATORIES, SHUTDOWN, THERMAL REACTORS, US AEC, US ERDA, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue