The effects of aging on Boiling Water Reactor core isolation cooling system
Conference
·
OSTI ID:10157066
A study was performed to assess the effects of aging on the Reactor Core Isolation Cooling system in commercial Boiling Water Reactors. This study is part of the Nuclear Plant Aging Research program sponsored by the US Nuclear Regulatory Commission. The failure data, from national databases, as well as plant specific data were reviewed and analyzed to understand the effects of aging on the RCIC system. This analysis identified important components that should receive the highest priority in terms of aging management. The aging characterization provided information on the effects of aging on component failure frequency, failure modes, and failure causes.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10157066
- Report Number(s):
- BNL-NUREG-60269; CONF-940613-23; ON: DE94013028; TRN: 94:012937
- Resource Relation:
- Conference: 1994 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference,Minneapolis, MN (United States),19-23 Jun 1994; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
AGING
FAILURES
DATA ANALYSIS
PUMPS
VALVES
TURBINES
FAILURE MODE ANALYSIS
REACTOR SAFETY
210100
220900
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
AGING
FAILURES
DATA ANALYSIS
PUMPS
VALVES
TURBINES
FAILURE MODE ANALYSIS
REACTOR SAFETY
210100
220900
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED