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