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A verification of a thermohydraulic computer code for PWR steam generators

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5564721
;
None
Research Organization:
Westinghouse Electric Corporation, Nuclear Energy Systems, P.O. Box 855, Pittsburgh, PA 15230
OSTI ID:
5564721
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
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
220200* -- Nuclear Reactor Technology-- Components & Accessories
ACCURACY
BOILERS
BOUNDARY CONDITIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
FLOW MODELS
FLUID MECHANICS
HEAT FLUX
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTORS
SIMULATION
STEAM GENERATORS
T CODES
TEMPERATURE DISTRIBUTION
THERMODYNAMICS
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS