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A momentum integral network method for thermal-hydraulic transient analysis

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5510726
None
Research Organization:
Brookhaven National Laboratory, Upton, NY 11973
OSTI ID:
5510726
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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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPRESSIBLE FLOW
COMPUTER CALCULATIONS
COMPUTER CODES
EPITHERMAL REACTORS
EXPANSION
FAST REACTORS
FBR TYPE REACTORS
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
LIQUID METAL COOLED REACTORS
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MATHEMATICAL MODELS
MECHANICS
NETWORK ANALYSIS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
REACTOR SAFETY
REACTORS
SAFETY
SODIUM COOLED REACTORS
THERMAL EXPANSION
THERMAL POWER PLANTS
THERMODYNAMICS
TRANSIENTS