COBRA/TRAC simulation of a semiscale small-break LOCA
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5159228
None
- Research Organization:
- Battelle-Pacific Northwest Laboratory P.O. Box 999 Richland, WA 99352
- OSTI ID:
- 5159228
- Report Number(s):
- CONF-831047-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
- Country of Publication:
- United States
- Language:
- English
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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
BOILERS
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
STEADY-STATE CONDITIONS
STEAM GENERATORS
T CODES
THERMODYNAMICS
TWO-PHASE FLOW
VAPOR GENERATORS
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
BOILERS
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
STEADY-STATE CONDITIONS
STEAM GENERATORS
T CODES
THERMODYNAMICS
TWO-PHASE FLOW
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS