Sensitivity and uncertainty analyses in aging risk-based prioritizations
- Brookhaven National Lab., Upton, NY (United States)
- Science Applications International Corp., Dublin, OH (United States)
Aging risk evaluations of nuclear power plants using Probabilistic Risk Analyses (PRAs) involve assessments of the impact of aging structures, systems, and components (SSCs) on plant core damage frequency (CDF). These assessments can be used to prioritize the aging risk contributors reflecting the relative risk potential of the SSCs. Aging prioritization are important for identification of SSCs most contributing to plant risk and can provide a systematic basis on which aging risk control and management strategies for a plant can be developed. These prioritizations are, however, subject to variabilities arising from uncertainties in data and/or from various modeling assumptions. The objective of this paper is to present an evaluation of the sensitivity of aging prioritizations of active components to uncertainties in aging risk quantifications. Approaches for robust prioritization of SSCs are also presented which are less susceptible to the uncertainties.
- 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:
- 10102251
- Report Number(s):
- BNL-NUREG-48994; CONF-940312-3; ON: DE93015785; TRN: 94:001314
- Resource Relation:
- Conference: 2. Probabilistic safety assessment and management conference (PSAM),San Diego, CA (United States),20-24 Mar 1994; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
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