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Interfacing system LOCAs at PWRs (pressurized water reactors): A new assessment

Conference ·
OSTI ID:5194854
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Interfacing system loss-of-coolant accidents (ISL) were first identified and analyzed in the Reactor Safety Study (RSS). ISLs were found to be significant contributors to the risk estimates for the presurized water reactor (PWR) analyzed in the RSS. Some evaluations of ISL sequences in subsequent studies have also found that their contribution to risk is also significant. ISLs are potentially important to risk because a direct path is opened from the damaged reactor core which bypasses the containment building. Thus, these sequences can potentially result in a signfiicant fission product release to the environment. In spite of the numerous analyses conducted in various Probabilistic risk Assessment (PRA) Studies during recent years, the models and assumptions used to describe ISLs are subject to substantial uncertainties. In addition, recent studies performed within the framework of the Industry Degraded core Rulemaking Program (IDCOR) indicate that previous ISL analyses may result in overly conservative results. 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 the ISL sequences at PWRs has been performed at Brookhaven National Laboratory.
Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5194854
Report Number(s):
BNL-NUREG-40754; CONF-880601-16; ON: DE88006291
Country of Publication:
United States
Language:
English

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