PRAAGE-1988: An interactive IBM-PC code for aging analysis of NUREG-1150 systems
Probabilistic Risk Assessments (PRA) contain a great deal of information for estimating the risk of a nuclear power plant but do not consider aging. PRAAGE (PRA+AGE) is an interactive, IBM-PC code for processing PRA-developed system models using non-aged failure rate data in conjunction with user-supplied time-dependent nuclear plant experience component failure rate data to determine the effects of component aging on a system's reliability as well as providing the age-dependent importances of various generic components. This paper describes the structure, use and application of PRAAGE to the aging analysis of the Peach Bottom 2 RHR system in the LPCI and SDC modes of operation. 4 refs., 15 figs., 5 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6493345
- Report Number(s):
- BNL-NUREG-42169; CONF-8810155-39; ON: DE89006173
- Resource Relation:
- Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AGING
P CODES
NUCLEAR POWER PLANTS
AFTER-HEAT REMOVAL
FAILURES
IBM COMPUTERS
PERSONAL COMPUTERS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
MICROCOMPUTERS
NUCLEAR FACILITIES
POWER PLANTS
REMOVAL
SAFETY
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories