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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.
Heinz E. Haefner
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 69-74
Technical Paper | Fuel | doi.org/10.13182/NT77-A31830
Articles are hosted by Taylor and Francis Online.
Designing advanced fuel element concepts for fast breeder reactors and assessing by models the fuel rod behavior over the intended in-pile time require information about creeping and swelling in the nuclear fuels under in-pile conditions. For this reason, a number of in-pile facilities that allow such material data to be determined have been used at the Karlsruhe Nuclear Research Center. These data depend not only on the properties of the fuel, above all the type of fuel and its density, but also, and in a very decisive way, on such parameters as specimen temperature, specimen loading, and burnup. A new series of experiments serves the concrete purpose of a quantitative assessment of the dependence on these parameters of carbides as potential fast breeder fuels, carbides being more susceptible to swelling than oxides. The loading of the specimen is given by the cladding restraint with the swelling fuel, and does not cause any undue expansion of the cladding of realistic fuel rods under operating conditions. This permissible