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Yang, J.W.; Pratt, W.T.
International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-161985
International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-161985
AbstractAbstract
[en] A probabilistic risk assessment and consequence analysis for a BWR with a Mark-II containment design has shown that overpressurization is the dominant containment failure mode for a wide range of potential core meltdown accidents. This failure mode is a major contributor to the predicted off-site health consequences. Mitigation of this failure mode is aimed at maintaining the containment integrity by using a wetwell venting system and a drywell spray system. Detailed analyses with the MARCH 2 code were used to determine the effectiveness of the mitigating features. The results show that the wetwell venting system is capable of preventing overpressurization in the containment and the drywell spray system is needed to reduce the corium/concrete interactions. However, additional mitigating systems are required for long-term cooling of the corium and ultimate removal of the decay heat for the ATWS case
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Electric Power Research Inst., Palo Alto, CA (USA); p. 120.1-120.11; Feb 1985; p. 120.1-120.11; International ANS/ENS topical meeting on probabilistic safety methods and applications; San Francisco, CA (USA); 24 Feb - 1 Mar 1985; Research Reports Center, P.O. Box 50490, Palo Alto, CA 94303 $125.00
Record Type
Report
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Conference
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AFTER-HEAT REMOVAL, ATWS, BNL, CONCRETES, CONTAINMENT SPRAY SYSTEMS, CONTAINMENT SYSTEMS, CORIUM, ECCS, FAILURES, LIMERICK-1 REACTOR, LIMERICK-2 REACTOR, M CODES, MELTDOWN, PRESSURE SUPPRESSION, PRESSURIZATION, PROBABILITY, REACTOR ACCIDENTS, REACTOR CORE DISRUPTION, REACTOR SAFETY, RISK ASSESSMENT, VALVES
ACCIDENTS, BUILDING MATERIALS, BWR TYPE REACTORS, COMPUTER CODES, CONTAINMENT, CONTROL EQUIPMENT, DESIGN BASIS ACCIDENTS, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, MATERIALS, NATIONAL ORGANIZATIONS, POWER REACTORS, REACTOR PROTECTION SYSTEMS, REACTORS, SAFETY, THERMAL REACTORS, US AEC, US DOE, US ERDA, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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