Development of a policy for the use of PRA (Probabilistic Risk Assessment) in the deployment of advanced LWRs and for addressing severe accident considerations

Conference · Thu May 21 00:00:00 EDT 1987

OSTI ID:5447280

Stiger, R R; Leaver, D E; von Herrmann, J L; Krantz, E; Davis, P R; Fuoto, J S; Mattson, R J; Summitt, R L

In 1985, the US Department of Energy initiated the Advanced Reactor Severe Accident Program (ARSAP). An overall objective of ARSAP is to resolve severe accident issues as they apply to advanced light water reactor (ALWR) design certification. A portion of ARSAP involves evaluating the use of, and establishing methodology for, the application of Probabilistic Risk Assessment (PRA) to these designs. This paper discusses the results of an effort to identify appropriate applications of PRA to ALWRs including examples.

• Research Organization: IT-Delian Corp., Monroeville, PA (USA); PRD Consulting (USA); International Energy Associates Ltd., Fairfax, VA (USA); IT Corp., Pittsburgh, PA (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5447280
• Report Number(s): EGG-M-14387; CONF-870820-10; ON: DE88006757; TRN: 88-013110
• Resource Relation: Conference: PSA 87: international topical meeting on probabilistic safety assessment and risk management, Zurich, Switzerland, 31 Aug 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WATER COOLED REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
CONTAINMENT
DESIGN
REACTIVITY
REACTOR COOLING SYSTEMS
RELIABILITY
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Nonboiling Water Cooled