Published 1986
| Version v1
Book
IDCOR methodology for individual plant evaluation
- 1. Fauske and Associates, Inc., 16W070 West 83rd Street, Burr Ridge, IL 60521
Description
The NRC policy statement on severe accidents requires that a vulnerability study be performed on all plants. This should address both the core damage prevention capability and the fission product retention capacity for a given primary system and containment. The industry sponsored IDCOR Program has developed a methodology for performing these assessments for both BWR and PWR systems. This paper discusses the basic approach developed in the methodology
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-121-5
- Imprint Title
- Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
- Journal Page Range
- p. III2.1-III2.8.
Conference
- Title
- International ANS/ENS topical meeting on thermal reactor safety.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080459
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT; ENERGY POLICY; FISSION PRODUCT RELEASE; I CODES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; US NRC
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS