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

Abstract

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.

Authors:
; ;  [1]
  1. Science Applications International Corp., Columbus, OH (USA)
Publication Date:
Research Org.:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Science Applications International Corp., Columbus, OH (USA)
Sponsoring Org.:
USNRC
OSTI Identifier:
6756739
Report Number(s):
NUREG/CR-5510; SAIC-89/1744
ON: TI90013694; TRN: 90-028842
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Vesely, W E, Kurth, R E, and Scalzo, S M. Evaluations of core melt frequency effects due to component aging and maintenance. United States: N. p., 1990. Web. doi:10.2172/6756739.
Vesely, W E, Kurth, R E, & Scalzo, S M. Evaluations of core melt frequency effects due to component aging and maintenance. United States. https://doi.org/10.2172/6756739
Vesely, W E, Kurth, R E, and Scalzo, S M. 1990. "Evaluations of core melt frequency effects due to component aging and maintenance". United States. https://doi.org/10.2172/6756739. https://www.osti.gov/servlets/purl/6756739.
@article{osti_6756739,
title = {Evaluations of core melt frequency effects due to component aging and maintenance},
author = {Vesely, W E and Kurth, R E and Scalzo, S M},
abstractNote = {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.},
doi = {10.2172/6756739},
url = {https://www.osti.gov/biblio/6756739}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 1990},
month = {Fri Jun 01 00:00:00 EDT 1990}
}