Published October 1991 | Version v1
Report

Generic framework for IPE back-end (level 2) analysis. Volume 3: BWR implementation guidelines. Final report, October 1991

Description

A methodology has been developed to support utilities performing Individual Plant Examination (IPE) back-end analyses. The methodology consists of severe accident progression logic models with implementation guidelines for typical Light Water Reactor (LWR) nuclear power plants. The guidelines address how these logic models can be applied for the plant under examination when using existing severe accident analyses. Also, the generic framework complements EPRI's MAAP computer program, a deterministic severe accident analysis code, by providing a logic model for evaluating containment response to postulated severe accident loads, plant damage state binning criteria and other probabilistic portions of IPE back-end analysis. (author)

Availability note (English)

Available from Research Reports Center (RRC), PO Box 50490, Palo Alto, CA 94303 (United States)

Additional details

Publishing Information

Imprint Pagination
178 p.
Report number
NSAC--159(v.3)

INIS

Country of Publication
United States
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34002201
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; CONTAINMENT SYSTEMS; M CODES; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Refs, figs, tabs