NUREG/CR-5587, "Approaches for Age-Dependent Probabilistic Safety Assessments with Emphasis on Prioritization and Sensitivity Studies."
نویسنده
چکیده
Approaches are described for incorporating component aging reliability models into a probabilistic safety assessment (PSA), or probabilistic risk assessment (PRA), of a nuclear power plant. These approaches and procedures are described from a technical standpoint and are not to be interpreted as having any regulatory implications. Component aging failure rate models and test and maintenance aging control models are presented for utilization. Different approaches for carrying out the aging evaluations are given. Demonstrations are given involving prioritizing aging contributors, evaluating maintenance effectiveness, carrying out time dependent evaluations, and carrying out uncertainty and sensitivity analyses of aging effects.
منابع مشابه
NUREG/CR-5378, "Aging Data Analysis and Risk Assessment Development and Demonstration Study."
This work develops and demonstrates a probabilistic risk assessment (PRA) approach to assess the effect of aging and degradation of active components on plant risk. The work (a) develops a way to identify and quantify age-dependent failure rates of active components, and to incorporate them into PRA; (b) demonstrates these tools by applying them to a fluid-mechanical system, using the key eleme...
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