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Best-estimate analysis of a loss-of-coolant accident in a typical US PWR using TRAC

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5744554
; ;
None
Research Organization:
Los Alamos Scientific Lab., NM
OSTI ID:
5744554
Report Number(s):
CONF-790602-(Summ.)
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS