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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT REMOVAL
AGING
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
FAILURES
IBM COMPUTERS
MICROCOMPUTERS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
P CODES
PERSONAL COMPUTERS
POWER PLANTS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
REMOVAL
RISK ASSESSMENT
SAFETY
THERMAL POWER PLANTS