Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, November 1, 1972 - January 31, 1973)
The tasks of the Gas-Cooled Fast Breeder Reactor (GCFR) program that are supported by the U.S. Atomic Energy Commission are program planning, core development, development of a pressure equalization system for fuel rods, fuels and materials development, and nuclear analysis and reactor physics. Core development work included analytical studies of the effects of fuel-rod spacer grid misalignment, the design and start of construction of a fuel-rod—spacer wear and fretting test, the thermal-hydraulic performance of the GCFR fuel element, and a fuel-rod calculation model. A development program plan for the pressure equalization system was prepared. The status of the thermal- and fast-flux irradiation programs is given. The results to date of the fission-gas release data from the vented fuel rod GB-10 being irradiated in the ORR are given. Reactor physics work was concerned with critical assembly analysis of small-sample worths, comparing the results of GGA and ANL calculations of a 300~MW(e) GCFR core, and defining physics design problems of the GCFR.
- 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-28-010009
- OSTI ID:
- 4482884
- Report Number(s):
- GULF-GA--A12530
- 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
CONFIGURATION-- FUEL RODS-- PHYSICAL RADIATION EFFECTS-- REACTOR CORES-- SPACERS-- TESTING
CRITICALITY-- DELAYED NEUTRON FRACTION-- DOPPLER COEFFICIENT-- NEUTRON FLUX-- REACTIVITY WORTHS-- REACTOR KINETICS
DESIGN-- HEAT TRANSFER-- MELTING-- NATURAL CONVECTION-- PERFORMANCE-- REACTOR CORES-- THERMAL SHIELDS
FUEL DENSIFICATION
Fuel element
Fuel rod
Nuclear Criticality Safety Program (NCSP)
PLANNING FUEL DENSIFICATION-- FUEL RODS-- PHYSICAL RADIATION EFFECTS-- SOLID FUELS
Reactors--Power Reactors
Breeding
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONFIGURATION-- FUEL RODS-- PHYSICAL RADIATION EFFECTS-- REACTOR CORES-- SPACERS-- TESTING
CRITICALITY-- DELAYED NEUTRON FRACTION-- DOPPLER COEFFICIENT-- NEUTRON FLUX-- REACTIVITY WORTHS-- REACTOR KINETICS
DESIGN-- HEAT TRANSFER-- MELTING-- NATURAL CONVECTION-- PERFORMANCE-- REACTOR CORES-- THERMAL SHIELDS
FUEL DENSIFICATION
Fuel element
Fuel rod
Nuclear Criticality Safety Program (NCSP)
PLANNING FUEL DENSIFICATION-- FUEL RODS-- PHYSICAL RADIATION EFFECTS-- SOLID FUELS
Reactors--Power Reactors
Breeding