Published 1988 | Version v1
Book Metadata-only

Nuclear plant aging research on the high pressure injection system

Creators

  • 1. Idaho National Engineering Lab., Idaho Falls, ID (USA)

Description

This paper presents the results of a review of light water reactor high pressure injection system (HPIS) operating experiences reported in the nuclear power experience data base, licensee event reports, nuclear plant reliability data system, and plant records. The purpose of the review is to evaluate the potential significance of aging as a contributor to degradation of the HPIS. Tables are presented that show the percentage of events for HPIS classified by cause, component, and subcomponents for pressurized water reactors. A representative plant was selected for a detailed study. The U.S. Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identifies components susceptible to aging, stressors, degradation mechanisms, and failure modes for the HPIS

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. 325-331.

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
22056045
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; DATA BASE MANAGEMENT; FAILURE MODE ANALYSIS; LICENSING; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MONITORING SYSTEMS; RECOMMENDATIONS; RESEARCH PROGRAMS; US NRC
Descriptors DEC
ENRICHED URANIUM REACTORS; MANAGEMENT; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-880748--.