Gas-Cooled Fast Breeder Reactor. Quarterly progress report, August 1, 1975--October 31, 1975
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 Atomics, San Diego, CA (United States)
- DOE Contract Number:
- E(04-3)-167
- NSA Number:
- NSA-33-028022
- OSTI ID:
- 4057857
- Report Number(s):
- GA-A-13766
- Resource Relation:
- Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
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Gas-Cooled Fast Breeder Reactor. Quarterly progress report, November 1, 1975--January 31, 1976
Gas-cooled fast breeder reactor. Quarterly progress report, May 1, 1976--July 31, 1976
Related Subjects
Breeding
210500* -Nuclear Power Plants-Power Reactors
Breeding
*FUEL ELEMENTS- RESEARCH PROGRAMS
*GCFR REACTOR- REACTOR MATERIALS
*REACTOR COMPONENTS- RESEARCH PROGRAMS
*REACTOR MATERIALS- RESEARCH PROGRAMS
BREEDING BLANKETS
DESIGN
HEAT TRANSFER
HYDRAULICS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
SHIELDS
TESTING