Prediction of CHF in rod bundles using round-tube CHF correlation. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5317122
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5317122
- Report Number(s):
- CONF-791103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
- Country of Publication:
- United States
- Language:
- English
Similar Records
CHF predictions in rod bundles
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Wed Dec 31 23:00:00 EST 1980
· Trans. Am. Nucl. Soc.; (United States)
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OSTI ID:5091691
Rod bundle CHF at low pressure
Conference
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Thu Jun 01 00:00:00 EDT 1978
· Trans. Am. Nucl. Soc.; (United States)
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Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5224828
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
CRITICAL HEAT FLUX
FUEL ASSEMBLIES
HEAT FLUX
LOSS OF COOLANT
MATHEMATICAL MODELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
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SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS