GCFR core thermal-hydralic design
Conference
·
OSTI ID:5168524
The approach for developing the thermal-hydraulic core assembly designs for the gas-cooled fast reactor (GCFR) is reviewed, and key considerations for improving the core performance at all power and flow conditions are discussed. It is shown how the thermal-hydraulic core assembly designs evolve from evaluations of plant size, material limitations, safety criteria, and structural performance considerations.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76SF71023
- OSTI ID:
- 5168524
- Report Number(s):
- GA-A-15909; CONF-800648-18
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONFIGURATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HYDRAULICS
LIQUID FLOW
MECHANICS
PRESSURE GRADIENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
TEMPERATURE GRADIENTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONFIGURATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HYDRAULICS
LIQUID FLOW
MECHANICS
PRESSURE GRADIENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
TEMPERATURE GRADIENTS