Gas-Cooled Fast Breeder Reactor. Quarterly progress report, August 1, 1975--October 31, 1975

Technical Report · Thu Jan 01 04:00:00 EST 1976

DOI:https://doi.org/10.2172/4057857· OSTI ID:4057857

The tasks of the Gas-Cooled Fast Breeder Reactor (GCFR) program that are supported by the U. S. Energy Research and Development Administration include: development of GCFR fuel, blanket, and control elements; development of the pressure equilization system for GCFR fuel; an out-of-pile loop facility test program plan; 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 core support structure; development of reactor components including the reactor vessel, control and locking mechanisms, fuel-handling equipment, core support structure, shielding assemblies, main helium circulator, steam generator, and auxiliary circulator; the development of a helium circulator test facility; and reactor safety, including an in-pile safety evaluation program. (auth)

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• DOE Contract Number: E(04-3)-167
• NSA Number: NSA-33-028022
• OSTI ID: 4057857
• Report Number(s): GA-A--13766
• Country of Publication: United States
• Language: English

Related Subjects

*FUEL ELEMENTS-- RESEARCH PROGRAMS
*GCFR REACTOR-- REACTOR MATERIALS
*REACTOR COMPONENTS-- RESEARCH PROGRAMS
*REACTOR MATERIALS-- RESEARCH PROGRAMS
210500* --Nuclear Power Plants--Power Reactors
Breeding
BREEDING BLANKETS
DESIGN
HEAT TRANSFER
HYDRAULICS
N77500* --Reactors--Power Reactors
Breeding
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
SHIELDS
TESTING