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Improved modeling of heat removal in steam generators during PWR transients

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6809085
;
None
Research Organization:
EPRI, Palo Alto, CA 34303
OSTI ID:
6809085
Report Number(s):
CONF-801107-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 35
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
BOILERS
COMPUTER CODES
ENERGY TRANSFER
FEEDWATER
HEAT TRANSFER
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
R CODES
REACTORS
STEAM GENERATORS
TESTING
TRANSIENTS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS