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Theofanous, T.G.; Amarasooriya, W.H.; Yan, H.; Ratnam, U.
Eighteenth water reactor safety information meeting. Volume 2, Severe accident research, accident management, probabilistic risk assessment topics, individual plant examination program and other issues1991
Eighteenth water reactor safety information meeting. Volume 2, Severe accident research, accident management, probabilistic risk assessment topics, individual plant examination program and other issues1991
AbstractAbstract
[en] An integrated analysis of Mark-I liner attack in a postulated core melt accident is presented. The approach consists of the mechanistic treatment of the sequence of physical phenomena that lead to liner contact by corium debris, and their coupling through a probabilistic framework that allows representation of uncertainties. The authors emphasize a physically consistent treatment in each sequence, but allow for qualitatively different scenarios to represent the range of behavior due to model uncertainties. The results are presented in a format that allows their direct use in PRAs, and, in particular, expert opinion is incorporated by a new methodological approach (first applied in the study of α-mode failure-NUREG/CR-5030) that involves expert review of, and comment on, a fully documented study all under one cover. Details of the methodology (Risk Oriented Accident Analysis Methodology-ROAAM) are also presented
Primary Subject
Source
Weiss, A.J. (comp.) (Brookhaven National Lab., Upton, NY (USA)); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States); 578 p; Apr 1991; p. 343-361; 18. water reactor safety information meeting; Rockville, MD (United States); 22-24 Oct 1990; CONF-9010185--VOL.2; OSTI as TI91011738; NTIS; INIS; GPO
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
BWR TYPE REACTORS, CONTAINMENT SYSTEMS, CORIUM, DYNAMIC LOADS, FAILURES, FUEL-COOLANT INTERACTIONS, HEAT TRANSFER, HEATING, HYDRAULICS, LINERS, MELTDOWN, PROBABILISTIC ESTIMATION, REACTOR ACCIDENTS, REACTOR CORE DISRUPTION, REACTOR SAFETY, RELIABILITY, RISK ASSESSMENT, SENSITIVITY, TIME DEPENDENCE, US NRC
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue