Gas-cooled fast breeder reactor. Quarterly progress report, November 1, 1977--January 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety]

Technical Report · Wed Feb 01 00:00:00 EST 1978

DOI:https://doi.org/10.2172/5011249· OSTI ID:5011249

Progress is summarized 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; 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; and development of a reliability data bank.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: EY-76-C-03-0167-023
• OSTI ID: 5011249
• Report Number(s): GA-A-14771
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
DESIGN
ENGINEERING
BREEDING BLANKETS
CONTROL ELEMENTS
FLUID FLOW
FUEL ELEMENTS
HEAT TRANSFER
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SAFETY
RESEARCH PROGRAMS
SHIELDING
STRESS ANALYSIS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
KINETICS
REACTORS
SAFETY
210500* - Power Reactors
Breeding