Risk evaluation of the containment overpressure relief system in a BWR-4, Mark-II nuclear power plant
Conference
·
OSTI ID:5701553
The purpose of this paper is to present a risk evaluation of a Containment Overpressure Relief (COR) system in a BWR-4, Mark-II nuclear power plant. The evaluation is done relative to three risk indices that are related to the frequency of core damage, the early fatalities, and the latent fatalities that might result from an accident in the plant. The evaluation of the COR is based on the Probabilistic Risk Assessment Study of the Limerick Generating Station as it was revised by BNL. Two analyses were performed; one assumes that the design of the plant does not include the COR system and the other assumes that it is included. The risk indices are evaluated in both cases and compared.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5701553
- Report Number(s):
- BNL-NUREG-33295; CONF-831047-47; ON: DE83014767
- Country of Publication:
- United States
- Language:
- English
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