Gas-Cooled Fast Breeder Reactor. Quarterly progress report, May 1, 1975-- July 31, 1975
Technical Report
·
OSTI ID:4088903
Progress is described in the areas of development of GCFR fuel, blanket, and control elements; fuels and materials development; nuclear analysis and reactor physics for GCFR core design; development of the pressure-equalization system for GCFR fuel; structural-thermal-flow tests of core assemblies; an in- pile loop facility test program plan; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and core support structure, development of reactor control-rod, shutdown-rod, and core element locking mechanisms, evaluation of the capability of PCRV internal structures for postaccident fuel containment; evaluation of the pressure-boundary integrity of the prestressed concrete reactor vessel (PCRV); reactor safety; refueling-system development; component development engineering; shielding requirements of the GCFR; and fuel-rod engineering to evaluate the steady-state and transient performance of the GCFR fuel and blanket rods. (auth)
- Research Organization:
- General Atomic Co., San Diego, Calif. (USA)
- DOE Contract Number:
- E(04-3)-167
- NSA Number:
- NSA-33-019481
- OSTI ID:
- 4088903
- Report Number(s):
- GA-A--13565
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*FUEL ELEMENTS-- VENTS
*GCFR REACTOR-- SHIELDING
*IN PILE LOOPS-- PLANNING
*REACTOR CORES-- STRESS ANALYSIS
*SHIELDS-- RADIATION HEATING
210500* --Nuclear Power Plants--Power Reactors
Breeding
ADHESION
BREEDING BLANKETS
CONFIGURATION
CONTAINERS
DEFORMATION
DESIGN
FISSION PRODUCTS
FRICTION
FUEL-CLADDING INTERACTIONS
GAS FLOW
HEAT TRANSFER
HELIUM
IRRADIATION CAPSULES
LEAK TESTING
MELTING
N77500* --Reactors--Power Reactors
Breeding
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
POROSITY
PRESSURE GRADIENTS
PRESTRESSED CONCRETE
PRIMARY COOLANT CIRCUITS
RADIATION MONITORING
REMOVAL
RESEARCH PROGRAMS
SEALS
SPACERS
STAINLESS STEEL-316
THERMAL INSULATION
THERMAL STRESSES
*GCFR REACTOR-- SHIELDING
*IN PILE LOOPS-- PLANNING
*REACTOR CORES-- STRESS ANALYSIS
*SHIELDS-- RADIATION HEATING
210500* --Nuclear Power Plants--Power Reactors
Breeding
ADHESION
BREEDING BLANKETS
CONFIGURATION
CONTAINERS
DEFORMATION
DESIGN
FISSION PRODUCTS
FRICTION
FUEL-CLADDING INTERACTIONS
GAS FLOW
HEAT TRANSFER
HELIUM
IRRADIATION CAPSULES
LEAK TESTING
MELTING
N77500* --Reactors--Power Reactors
Breeding
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
POROSITY
PRESSURE GRADIENTS
PRESTRESSED CONCRETE
PRIMARY COOLANT CIRCUITS
RADIATION MONITORING
REMOVAL
RESEARCH PROGRAMS
SEALS
SPACERS
STAINLESS STEEL-316
THERMAL INSULATION
THERMAL STRESSES