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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
C. T. Walker, S. Pickering
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 207-215
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32151
Articles are hosted by Taylor and Francis Online.
Analyses were performed on three mixed-oxide fuel pins. Two were irradiated in a fast flux, one in an epithermal-neutron flux. The compositions of the corrosion product phases in the fuel-cladding gaps of the different pins were similar. The phase was essentially a mixture of metal oxides, with chromium oxide the main constituent. Cesium chromate, if it formed at all, was present in only small amounts. Oxides of iron and nickel were not detected, which suggests that the oxygen potential in the gap did not exceed that for the FeCr2O4 formation. Metallic fragments in the phase resulted from mechanical interactions involving the phase and cladding grains whose boundaries had been weakened by intergranular corrosion. Chromium and manganese were lost from the inner cladding surface of all three pins. Titanium loss also occurred from the two pins clad with titanium-stabilized steel. A grain boundary phase depleted in chromium was present at the inner cladding surface of one of the pins irradiated in a fast flux. The phase that was associated with intergranular attack occurred in advance of the corrosion front.