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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.
D. R. Duncan
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 199-206
Technical Paper | Material | doi.org/10.13182/NT78-A32078
Articles are hosted by Taylor and Francis Online.
Creep rates of metals can be greatly enhanced by neutron irradiation experienced in a fast reactor en vironment. Because irradiation-induced creep strains can be large in magnitude for duct and cladding components, the effect of irradiation creep on subsequent mechanical property behavior must be quantified to provide a design base for core component performance assessment. Pressurized tubes that had sustained a peak value of irradiation creep strain of 1.04% and peak fast fluences of 10 X 1022 n/cm2 under irradiation in the Experimental Breeder Reactor II from 650 to 857 K were tested in subsequent transient burst loading. Results of testing show that subsequent deformation, is unaffected by prior irradiation creep within experimental error.