Published 1988
| Version v1
Book
Aging and life extension assessment of component cooling water systems
Creators
- 1. Brookhaven National Lab., Upton, NY (USA)
Description
An aging assessment of component cooling water systems in pressurized water reactors was performed as part of the Nuclear Regulator Commission's Nuclear Plant Aging Research (NPAR) program. Failure data from national data bases were analyzed and predominant failure modes, causes and mechanisms were identified. Plant specific data were also obtained to supplement and validate the data base results. Time-dependent failure rates calculated from the data show a trend toward increasing with age. Using these failure rates in probabilistic risk assessment type analyses, changes in component relative importance and system unavilability with age were observed. These findings are discusses in relation to plant life extension
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-139-8
- Imprint Title
- Proceedings of the topical meeting on nuclear power plant life extension
- Imprint Pagination
- 645 p.
- Journal Page Range
- p. 318-324.
Conference
- Title
- American Nuclear Society (ANS) topical meeting on nuclear power plant life extension.
- Dates
- 31 Jul - 3 Aug 1988.
- Place
- Snowbird, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22056142
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; ALGORITHMS; DATA BASE MANAGEMENT; FAILURE MODE ANALYSIS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; TIME DEPENDENCE; US NRC
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-880748--.