Evaluations of core melt frequency effects due to component aging and maintenance

Technical Report · Fri Jun 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6756739· OSTI ID:6756739

Vesely, W E; Kurth, R E; Scalzo, S M ^[1]

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1. Science Applications International Corp., Columbus, OH (USA)

A methodology is developed to incorporate aging effects into a Probabilistic Risk Analysis (PRA). The methodology separates the PRA models from the aging models, allowing available PRAs to be efficiently used in evaluating risk effects of aging. The methodology is applied to two PRAs to demonstrate the results which are obtainable from current PRAs. Various component aging rates and various surveillance and maintenance programs are evaluated to determine their impacts on the resulting core melt frequency. Both point evaluations and uncertainty evaluations are carried out. The results of the applications show that for given aging rates, the core melt frequency impacts are very sensitive to the surveillance and maintenance program which is carried out. The detailed results which are obtained allow the aging contributors to be effectively prioritized to focus aging management programs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Science Applications International Corp., Columbus, OH (USA)
• Sponsoring Organization: USNRC
• OSTI ID: 6756739
• Report Number(s): NUREG/CR-5510; SAIC-89/1744; ON: TI90013694; TRN: 90-028842
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
REACTOR COMPONENTS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
AGING
MAINTENANCE
COMPILED DATA
CORIUM
DATA BASE MANAGEMENT
FAILURES
FREQUENCY ANALYSIS
HEAT TRANSFER
HYDRAULICS
MELTDOWN
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MANAGEMENT
MECHANICS
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990300 - Information Handling