The objective of the F-l (X094) fast-flux experiment being irradiated in EBR-II is to study (U,Pu)O2 fuel-rod specimens with cladding temperatures in the range of 650°C to 800°C and at linear power-generation rates of 14 to 16 kW/ft. The F-l (X094) subassembly started irradiation in March 1971. At 50,000 MWd/Te burnup, five of the seven capsules will be removed and replaced with unirradiated encapsulated fuel rods. The mixed-oxide fuel is contained in 20% cold-worked Type 316 stainless steel and will achieve burnups ranging from 5.3 to 10.7% FIMA. The capsules are, in general, the Mark B-7B type with a stainless steel annular thermal barrier sodium-bonded to the fuel rod and to the capsule tube. Silicon carbide temperature mon¬itors and dosimeters are placed in various positions along the thermal barrier to allow postirradiation determination of capsule temperatures utilizing dimensional changes during isochronal annealing of the SiC and to determine axial flux distribution by dosimetry analysis. All of the fuel rods will contain activated charcoal traps to determine the effects of fast-neutron irradiation on the sorption characteristics of the charcoal for fission products.
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