An evaluation of ATWS core damage frequency for a BWR/4
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5062747
None
- Research Organization:
- Brookhaven National Lab., Upton, NY
- OSTI ID:
- 5062747
- Report Number(s):
- CONF-850610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 49
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of ATWS core damage frequency for a BWR/4
Evaluation of ATWS core damage frequency for an earlier vintage BWR/4
ATWS considerations relative to the BWR
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5633273
Evaluation of ATWS core damage frequency for an earlier vintage BWR/4
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:6476671
ATWS considerations relative to the BWR
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5351336
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
ATWS
BWR TYPE REACTORS
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS