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BWR containment failure analysis during degraded core accidents

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6661709
None
Research Organization:
NRC, Washington, DC
OSTI ID:
6661709
Report Number(s):
CONF-820609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 41
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURE MODE ANALYSIS
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
LOSS OF COOLANT
MELTDOWN
REACTOR ACCIDENTS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS