Sensitivity and uncertainty analyses in aging risk-based prioritizations [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1993. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 5 pages : digital, PDF file
- Additional Creators:
- Brookhaven National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- 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 contributors to aging risk reflecting the relative risk potential of the SSCs. Aging prioritizations are important for identifying the SSCs contributing most to plant risk and can provide a systematic basis on which aging risk control and management strategies for a plant can be developed. However, these prioritizations are 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 also are presented which are less susceptible to the uncertainties.
- Published through SciTech Connect., 11/01/1993., "bnl-nureg--49610", " conf-940312--41", "DE94003010", 2. Probabilistic safety assessment and management conference (PSAM),San Diego, CA (United States),20-24 Mar 1994., and Vesely, W.E.; Hassan, M.; Uryas`ev, S.
- Funding Information:
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