COBRA-TF grid spacer heat transfer models
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6544186
- Research Organization:
- Battelle-Pacific Northwest Laboratory, P.O. Box 999, Richland, WA 99352
- OSTI ID:
- 6544186
- Report Number(s):
- CONF-840614-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 46; Conference: Annual meeting of the American Nuclear Society, New Orleans, LA, USA, 3 Jun 1984
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL ELEMENT CLUSTERS
LOSS OF COOLANT
FLOW BLOCKAGE
COMPUTER CODES
HEAT TRANSFER
SPACERS
PWR TYPE REACTORS
B CODES
C CODES
DENSITY
DROPLETS
FLOW RATE
ACCIDENTS
ENERGY TRANSFER
FUEL ASSEMBLIES
PARTICLES
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
FUEL ELEMENT CLUSTERS
LOSS OF COOLANT
FLOW BLOCKAGE
COMPUTER CODES
HEAT TRANSFER
SPACERS
PWR TYPE REACTORS
B CODES
C CODES
DENSITY
DROPLETS
FLOW RATE
ACCIDENTS
ENERGY TRANSFER
FUEL ASSEMBLIES
PARTICLES
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled