Risk evaluation of the alternate-3A modification to the ATWS prevention/mitigation system in a BWR-4, Mark-II power plant
Conference
·
OSTI ID:5691979
Purpose of this paper is to present a risk evaluation of the ATWS Alternate 3A modification (ATWS-3A) proposed by NRC staff in NUREG-0460 to the ATWS prevention/mitigation system in a BWR nuclear power plant. The evaluation is done relative to three risk indices: the frequency of core damage, the expected early fatalities, and the expected latent fatalities.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5691979
- Report Number(s):
- BNL-NUREG-33611; CONF-830816-37; ON: DE84000620
- Resource Relation:
- Conference: International meeting on light-water reactor severe accident evaluation, Cambridge, MA, USA, 28 Aug 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
RISK ASSESSMENT
ATWS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
MODIFICATIONS
ACCIDENTS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
RISK ASSESSMENT
ATWS
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
MODIFICATIONS
ACCIDENTS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled