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Realistic methodology for calculation of a loss-of-coolant accident

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5262638
; ; ;
None
Research Organization:
General Electric Company Nuclear Energy Division 175 Curtner Avenue San Jose, CA 95125
OSTI ID:
5262638
Report Number(s):
CONF-831047-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
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
COMPUTERIZED SIMULATION
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
G CODES
HEAT TRANSFER
HYDRAULICS
LICENSING
LOSS OF COOLANT
MECHANICS
POWER GENERATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR LICENSING
REACTOR PROTECTION SYSTEMS
REACTORS
REGULATIONS
S CODES
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS