Analysis of risk reduction methods for interfacing system LOCAs (loss-of-coolant accidents) at PWRs [electronic resource].

Published:: Upton, N.Y. : Brookhaven National Laboratory, 1988.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: Pages: 5 : digital, PDF file
Additional Creators:: Brookhaven National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

The Reactor Safety Study (WASH-1400) predicted that Interfacing System Loss-of-Coolant Accidents (ISL) events were significant contributors to risk even though they were calculated to be relatively low frequency events. However, there are substantial uncertainties involved in determining the probability and consequences of the ISL sequences. For example, the assumed valve failure modes, common cause contributions and the location of the break/leak are all uncertain and can significantly influence the predicted risk from ISL events. In order to provide more realistic estimates for the core damage frequencies (CDFs) and a reduction in the magnitude of the uncertainties, a reexamination of ISL scenarios at PWRs has been performed by Brookhaven National Laboratory. The objective of this study was to investigate the vulnerability of pressurized water reactor designs to ISLs and identify any improvements that could significantly reduce the frequency/risk of these events.

Report Numbers:

E 1.99:bnl-nureg-41320
E 1.99: conf-880601-38
conf-880601-38
bnl-nureg-41320

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Note:

Published through SciTech Connect.
01/01/1988.
"bnl-nureg-41320"
" conf-880601-38"
"DE88012518"
American Nuclear Society annual meeting, San Diego, CA, USA, 12 Jun 1988.
Fitzpatrick, R.; Bozoki, G.; Kohut, P.

Funding Information:

AC02-76CH00016

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