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U.S. Department of Energy
Office of Scientific and Technical Information

Gas-cooled fast breeder reactor. Quarterly progress report, November 1, 1976--January 31, 1977

Technical Report ·
DOI:https://doi.org/10.2172/7217155· OSTI ID:7217155
Progress is described in the areas of development of GCFR fuel, blanket, and control assemblies; development of the pressure equalization system for GCFR fuel; out-of-pile loop facility test programs; 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; systems engineering; 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; reactor safety, environment, and risk analyses, including planning and support of an in-pile and out-of-pile safety test program; nuclear island engineering design; and development of a reliability data bank.
Research Organization:
General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
EY-76-C-03-0167
OSTI ID:
7217155
Report Number(s):
GA-A-14240
Country of Publication:
United States
Language:
English