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AbstractAbstract
[en] Level 2 probabilistic safety analysis (PRA) can be extremely costly. There are several options that can be used to avoid the high expenditures of time and money to obtain Level 2 insights. With reduced expenditure comes reduced insight into the behavior of specific parameters that contribute to containment failure and large source terms. If the primary objective of a study is quantitative, and does not require insights concerning the complex interactions among physical parameters and system parameters, a reduced scope method can be acceptable. If primary objectives require the understanding of the relative importance of specific physical processes and the complex interactions among the processes, reduced scope methods should not be used
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. 319-334; 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
Literature Type
Conference
Report Number
Country of publication
BWR TYPE REACTORS, BYPASSES, CONTAINMENT SYSTEMS, CORIUM, EXTRAPOLATION, FAILURE MODE ANALYSIS, FAILURES, FUEL-COOLANT INTERACTIONS, HYDROGEN, M CODES, MELTDOWN, MOLTEN METAL-WATER REACTIONS, PROBABILISTIC ESTIMATION, PWR TYPE REACTORS, R CODES, REACTOR CORE DISRUPTION, REACTOR SAFETY, RESEARCH PROGRAMS, RISK ASSESSMENT, S CODES, SOURCE TERMS, US NRC
ACCIDENTS, COMPUTER CODES, CONTAINMENT, ELEMENTS, ENRICHED URANIUM REACTORS, NATIONAL ORGANIZATIONS, NONMETALS, NUMERICAL SOLUTION, POWER REACTORS, REACTOR ACCIDENTS, REACTORS, SAFETY, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, THERMAL REACTORS, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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INIS VolumeINIS Volume
INIS IssueINIS Issue