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Journal Article

Citation

Brooks AC. Reliab. Eng. 1985; 13(3): 157-162.

Copyright

(Copyright © 1985, Elsevier Publishing)

DOI

10.1016/0143-8174(85)90092-7

PMID

unavailable

Abstract

A mini probabilistic risk assessment was performed in three stages to determine the reduction in core melt frequency due to a core rescue system. The core rescue system is intended to provide a means completely independent from normal ECCS systems of flooding the reactor core and removing decay heat.

The first stage was to determine the dominant core melt sequences for the reference plant (a Westinghouse three loop PWR) without the core rescue system. This was done by comparing the reference plant design with the designs analyzed in six PRAs on Westinghouse PWRs. The second stage was a standard fault tree analysis of the unavailability of various functions of the core rescue system. The third stage was to integrate the core rescue system analysis into the reference plant design and construct event trees to analyze the reduction in core melt frequency due to mitigation of the dominant sequences.

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