Whole-core thermal-hydraulic transient code development and verification for LMFBR analysis
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5715463
- Research Organization:
- Westinghouse Advanced Reactors Division, Madison, PA
- OSTI ID:
- 5715463
- Report Number(s):
- CONF-790602-(Summ.); TRN: 80-002034
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 32; Conference: ANS annual meeting, Atlanta, GA, USA, 3 Jun 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
TRANSIENTS
COMPUTER CODES
HEAT TRANSFER
HYDRAULICS
REACTOR CORES
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
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FLUID MECHANICS
LIQUID METAL COOLED REACTORS
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REACTOR COMPONENTS
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220900* - Nuclear Reactor Technology- Reactor Safety
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
TRANSIENTS
COMPUTER CODES
HEAT TRANSFER
HYDRAULICS
REACTOR CORES
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding