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Analysis of BWR fuel channel instability using a three-dimensional BWR core dynamics computer program

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5050936
;
None
Research Organization:
Hitachi Ltd. Energy Research Laboratory, 1168 Moriyama-cho, Hitachi-shi, Ibaraki 316, Japan
OSTI ID:
5050936
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
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL SYSTEMS
DATA ANALYSIS
FLOW MODELS
FLUID MECHANICS
FUEL CHANNELS
HYDRODYNAMICS
KINETICS
MATHEMATICAL MODELS
MECHANICS
P CODES
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR STABILITY
REACTORS
SIMULATION
STABILITY
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS