Published 1989 | Version v1
Book

Analysis of aging effect on active components at the N reactor

Creators

  • 1. Westinghouse Hanford Co., Richland, WA (United States)

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).

Optional Information

Secondary number(s)
CONF-890405--.