Published 1989
| Version v1
Book
Analysis of aging effect on active components at the N reactor
Description
This paper describes the aging analysis methodology developed during the N Reactor Level 1 Probabilistic Risk Assessment to help ensure the validity of a plant-specific component failure rate data base. A graphical technique was used on a system-by-system basis, plotting yearly failures, cumulative yearly failures, and the number of failures per hour for each year the reactor operated over a period of 11 years. Linear curve fits were developed for each data set and the trends of these curves were evaluated and compared. Examples of increasing failure rates attributable to aging were discovered, but engineering and maintenance practices at N Reactor have mitigated any potential consequences
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-142-8
- Imprint Title
- Probability, reliability, and safety assessment PSA '89
- Imprint Pagination
- 1300 p.
- Journal Page Range
- p. 1090-1096.
Conference
- Title
- international topical meeting on probability, reliability and safety assessment.
- Acronym
- PSA '89
- Dates
- 2-7 Apr 1989.
- Place
- Pittsburgh, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059333
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; EVALUATION; FAILURE MODE ANALYSIS; MITIGATION; N-REACTOR; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MAINTENANCE; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; MAINTENANCE; PLUTONIUM PRODUCTION REACTORS; POWER REACTORS; PRODUCTION REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-890405--.