CHF in fuel bundles at low mass velocities. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5224828
- EG and G Idaho, Inc., Idaho Falls, ID
None
- OSTI ID:
- 5224828
- 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
Prediction of CHF in rod bundles using round-tube CHF correlation. [PWR]
Rod bundle CHF at low pressure
CHF predictions in rod bundles
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Sun Dec 31 23:00:00 EST 1978
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·
OSTI ID:5317122
Rod bundle CHF at low pressure
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Thu Jun 01 00:00:00 EDT 1978
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Conference
·
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· Trans. Am. Nucl. Soc.; (United States)
·
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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
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS