Published 1987 | Version v1
Book Metadata-only

Development of a policy for the use of PRA in the development of advanced LWRs and for addressing severe accident considerations

Creators

  • 1. IT-Delian Corp., Idaho Falls, ID (USA)
  • 2. PRD Consulting, Idaho Falls, ID (USA)
  • 3. International Energy Associates Ltd., Fairfax, VA (USA)
  • 4. IT Energex, Oak Ridge, TN (USA)

Description

In 1985, the U.S. DOE 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. (orig./HSCH)

Additional details

Publishing Information

Publisher
Verl. TUEV Rheinland.
Imprint Place
Koeln (Germany, F.R.)
ISBN
3-88585-417-1
Imprint Title
Probabilistic safety assessment and risk management PSA '87. Vol. 3
Imprint Pagination
379 p.
Series
Risk and safety.
Journal Page Range
p. 862-868.

Conference

Title
International topical conference on probabilistic safety assessment and risk management (PSA '87).
Dates
31 Aug - 4 Sep 1987.
Place
Zurich (Switzerland).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
20061072
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; US DOE
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS