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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.
G. L. Ritter
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 194-202
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16311
Articles are hosted by Taylor and Francis Online.
The Purex solvent extraction process will be used in the nuclear fuel recovery and recycling center to reprocess up to 2100MT/yr of spent light water reactor fuels. Modifications to the process will be made to improve fission product decontamination and to treat gaseous and liquid radioactive waste streams. These modifications will allow overall decontamination factors for most fission products from recovered uranium and plutonium of >1010. No liquid process wastes will be released, and releases of radioactive materials in gaseous effluents will be as low as reasonably achievable.