Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, May 1, 1971-July 31, 1971)
The tasks of the AEC-supported Gas-Cooled Fast Breeder Reactor (GCFR) program are program planning, core development, fuels and materials development, irradiation tests, and nuclear analysis and reactor physics. The status of the three volumes of the development program plan document for the GCFR demonstration plant is reported. Surveillance of materials included some recent information on cladding materials, which is summarized. The current irradiation test results and analyses are reported for capsule GB-9, which is operating very satisfactorily in ORR and has reached 43,000 MWd/Te. Plans for the irradiation of a similar but improved capsule (GB-10) are discussed. The status of the fast-flux experiment F-l (X094) in EBR-II and of the five F-l replacement rods is reported. Results of out-of-pile experiments to develop cladding temperature-monitoring techniques are discussed. Finally, the background and objectives of the GCFR critical assembly program are presented.
- 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-26-003852
- OSTI ID:
- 4703247
- Report Number(s):
- GULF-GA--A10803
- Country of Publication:
- United States
- Language:
- English
Similar Records
Gas-Cooled Fast Breeder Reactor. Progress report, February 1, 1972--April 30, 1972
Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, August 1, 1972 - October 31, 1972)
Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, November 1, 1972 - January 31, 1973)
Technical Report
·
Thu Jul 20 00:00:00 EDT 1972
·
OSTI ID:4356734
Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, August 1, 1972 - October 31, 1972)
Technical Report
·
Thu Dec 07 23:00:00 EST 1972
·
OSTI ID:4490385
Gas-Cooled Fast Breeder Reactor (Quarterly Progress Report, November 1, 1972 - January 31, 1973)
Technical Report
·
Wed Mar 07 23:00:00 EST 1973
·
OSTI ID:4482884
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
BREEDER REACTORS
CRITICALITY
DISTRIBUTION
FAST REACTORS
FISSION PRODUCTS
FISSION RATIO
FUEL CANS
FUEL RODS
Fuel rod
GAS COOLED REACTORS
KRYPTON 85
KRYPTON 87
KRYPTON 88
Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PERFORMANCE
PLUTONIUM OXIDES
Power Reactor Development--Fuels
REACTOR CORE
STAINLESS STEELS
TESTING
Thermal flux
URANIUM DIOXIDE
XENON 133
XENON 135
ZPPR
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
BREEDER REACTORS
CRITICALITY
DISTRIBUTION
FAST REACTORS
FISSION PRODUCTS
FISSION RATIO
FUEL CANS
FUEL RODS
Fuel rod
GAS COOLED REACTORS
KRYPTON 85
KRYPTON 87
KRYPTON 88
Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PERFORMANCE
PLUTONIUM OXIDES
Power Reactor Development--Fuels
REACTOR CORE
STAINLESS STEELS
TESTING
Thermal flux
URANIUM DIOXIDE
XENON 133
XENON 135
ZPPR