Gas-Cooled Fast Breeder Reactor. Quarterly progress report, November 1, 1975--January 31, 1976

Technical Report · Mon Mar 22 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7361916· OSTI ID:7361916

Progress is reported in 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; development of a helium circulator test facility; and reactor safety, including an in-pile safety evaluation program.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• DOE Contract Number: E(04-3)-167
• OSTI ID: 7361916
• Report Number(s): GA-A-13815
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HEATING
HELIUM COOLED REACTORS
IN PILE LOOPS
PLANNING
RADIATION HEATING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SHIELDING
SHIELDS
STRESS ANALYSIS
VENTS