Gas-cooled fast breeder reactor. Quarterly progress report, May 1, 1976--July 31, 1976

Technical Report · Tue Aug 31 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7146567· OSTI ID:7146567

The tasks of the gas-cooled fast breeder reactor (GCFR) program include development of GCFR fuel, blanket, and control elements; development of the pressure equalization system for GCFR fuel; out-of-pile loop facility test program planning; fuels and materials development; fuel, blanket, and control rod analyses and development; nuclear analysis and reactor physics for GCFR core design; shielding requirements for the GCFR; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and the core support structure; plant systems control; development of reactor components, including reactor vessel, control and locking mechanisms, fuel handling equipment, core support structure, shielding assemblies, main helium circulator, steam generator, and auxiliary circulator; and reactor safety, including an in-pile safety evaluation program.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• OSTI ID: 7146567
• Report Number(s): GA-A-13975
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BLOWERS
BREEDER REACTORS
CONTAINERS
COOLING SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL CHANNELS
FUEL ELEMENTS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
KINETICS
MATHEMATICAL MODELS
PERFORMANCE TESTING
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SEALS
SHIELDING
SPACERS
TESTING