Approaches for age-dependent probabilistic safety assessments with emphasis on prioritization and sensitivity studies (in Rumanian)
- Science Applications International Corp., Dublin, OH (United States)
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.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Science Applications International Corp., Dublin, OH (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 7146570
- Report Number(s):
- NUREG/CR-5587; SAIC-92/1137; ON: TI92040803
- Country of Publication:
- United States
- Language:
- Rumanian
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Sensitivity and uncertainty analyses in aging risk-based prioritizations
Sensitivity and uncertainty analyses in aging risk-based prioritizations
Related Subjects
NUCLEAR POWER PLANTS
RISK ASSESSMENT
REACTOR COMPONENTS
AGING
FAILURES
MATHEMATICAL MODELS
REPAIR
SENSITIVITY ANALYSIS
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories