Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, August 1, 1972 - October 31, 1972)
The tasks of the Gas-Cooled Fast Breeder Reactor (GCFR) program supported by the U. S. Atomic Energy Commission are program planning, core development, development of pressure equalization system for fuel rods, fuels and materials development, and nuclear analysis and reactor physics. Core development work included structural and thermal analyses of the fuel element assembly, studies of the effects of fuel hot-pressing with burnup on fuel temperature, development of an analytical model for the monitor station instrumentation for the pressure equalization system, and further criticality studies of the lower shield assembly. Work on the planning document for the pressure equalization system for the fuel rods was initiated. In fuels and materials development, the status of the thermal-flux and fast-flux irradiation programs are given. The results of post-irradiation examinations to date of the GB-9 fuel rod irradiated in the thermal flux of the ORR and of the G-3 fuel rod irradiated in the EBR-II fast flux are given. Reactor physics studies included critical assembly analysis, in particular, calculations of small-sample worths, Doppler worth, βeff and prompt lifetime, and the conversion to ENDF/B Version III for GCFR calculations.
- Research Organization:
- Gulf General Atomic Co., San Diego, CA (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AT(04-3)-167
- NSA Number:
- NSA-28-004539
- OSTI ID:
- 4490385
- Report Number(s):
- GULF-GA--A12421
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*GCFR REACTOR-- RESEARCH PROGRAMS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
Axial
CONFIGURATION-- FUEL ASSEMBLIES-- FUEL DENSIFICATION-- FUEL RODS-- HOT PRESSING-- REACTOR CORES-- SPACERS-- TESTING
CRITICALITY-- DELAYED NEUTRON FRACTION-- DOPPLER COEFFICIENT-- REACTIVITY WORTHS-- REACTOR KINETICS
FUEL DENSIFICATION
Fuel element
Fuel rod
Nuclear Criticality Safety Program (NCSP)
PLANNING FUEL RODS-- MATERIALS TESTING-- PHYSICAL RADIATION EFFECTS-- SOLID FUELS-- URANIUM DIOXIDE
Reactors--Power Reactors
Breeding
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
Axial
CONFIGURATION-- FUEL ASSEMBLIES-- FUEL DENSIFICATION-- FUEL RODS-- HOT PRESSING-- REACTOR CORES-- SPACERS-- TESTING
CRITICALITY-- DELAYED NEUTRON FRACTION-- DOPPLER COEFFICIENT-- REACTIVITY WORTHS-- REACTOR KINETICS
FUEL DENSIFICATION
Fuel element
Fuel rod
Nuclear Criticality Safety Program (NCSP)
PLANNING FUEL RODS-- MATERIALS TESTING-- PHYSICAL RADIATION EFFECTS-- SOLID FUELS-- URANIUM DIOXIDE
Reactors--Power Reactors
Breeding