Comparison of the effect of hazard and response/fragility uncertainties on core melt probability uncertainty
This report proposes a method for comparing the effects of the uncertainty in probabilistic risk analysis (PRA) input parameters on the uncertainty in the predicted risks. The proposed method is applied to compare the effect of uncertainties in the descriptions of (1) the seismic hazard at a nuclear power plant site and (2) random variations in plant subsystem responses and component fragility on the uncertainty in the predicted probability of core melt. The PRA used is that developed by the Seismic Safety Margins Research Program.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6078591
- Report Number(s):
- UCID-20326; ON: DE85007212
- Country of Publication:
- United States
- Language:
- English
Similar Records
Validation of seismic probabilistic risk assessments of nuclear power plants
Seismic probabilistic risk assessment and seismic-margins studies for nuclear power plants. Technical report
Subsystem fragility: Seismic Safety Margins Research Program (Phase I)
Technical Report
·
Fri Dec 31 23:00:00 EST 1993
·
OSTI ID:10129434
Seismic probabilistic risk assessment and seismic-margins studies for nuclear power plants. Technical report
Technical Report
·
Mon Jun 15 00:00:00 EDT 1987
·
OSTI ID:5654118
Subsystem fragility: Seismic Safety Margins Research Program (Phase I)
Technical Report
·
Thu Oct 01 00:00:00 EDT 1981
·
OSTI ID:5507271