Examination of reflood heat transfer mechanisms using the FLECHT data. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7341007
None
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh
- OSTI ID:
- 7341007
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
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Mass effluence during FLECHT forced-reflood experiments. [PWR]
UCB experimental study of reflood heat transfer. [BWR, PWR]
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Tue Jun 01 00:00:00 EDT 1976
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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
DATA
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
HEAT TRANSFER
INFORMATION
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
REWETTING
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
DATA
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
HEAT TRANSFER
INFORMATION
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
REWETTING
WATER COOLED REACTORS
WATER MODERATED REACTORS