Fuel-cladding mechanical interaction in irradiated GCFR mixed-oxide fuel rods

Conference · Sun Oct 01 04:00:00 EDT 1978

OSTI ID:6223197

Chang, K. H.; Labar, M. P.

The Gas-Cooled Fast Breeder Reactor (GCFR) concept employs high-pressure (approximately 8.6 MPa) helium as the primary coolant. Among the unique characteristics of the GCFR fuel is the use of fuel rods which have roughened outside surfaces to enhance heat transfer and a system for pressure equalizing and venting the fuel rods. The irradiation test program for the GCFR fuel focuses on the evaluation of the unique parameters and features. One of the first of the test programs to complete irradiation was the F-1 experiment. The F-1 experiment, irradiated in EBR-II, consisted of 13 rods having prototypical geometry; one of the rods attained a burnup of 14 at. %. The primary distinguishing characteristics of the F-1 rods are that they were operated at relatively high cladding temperatures (to 760/sup 0/C) and relatively low internal rod pressures (maximum of 4.14 MPa). The F-1 cladding temperatures were designed to be characteristic of GCFR cladding temperatures (design hot spot temperature limit of 700/sup 0/C for normal events), and the rod internal pressures were maintained low to partially simulate the effect of the pressure equalization system. The combination of high cladding temperatures and low internal pressures in the F-1 rods provides insight into the performance characteristics of the GCFR fuel design. Information relevant to fast breeder reactor oxide fuels in general is also provided. The fuel rod-cladding mechanical behavior for the unique conditions in the F-1 rods, particularly with regard to fuel-cladding mechanical interaction (FCMI), is the subject of the paper. The analyses were carried out by means of the LIFE-3 computer program. Consequently, the calculated results when compared with the experimental data provide an additional verification of the LIFE-3 mechanical models employed in the high cladding temperature range.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: EY-76-C-03-0167-023
• OSTI ID: 6223197
• Report Number(s): GA-A-15176; CONF-790306-1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
IRRADIATION
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTOR COMPONENTS
REACTORS
TESTING
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES