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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.
Paul Naefe, Erich Zimmer
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 163-171
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Chemical Processing | doi.org/10.13182/NT79-A32147
Articles are hosted by Taylor and Francis Online.
A process has been developed for the production of dense fissile fuel kernels for the high-temperature reactor. A method is used whereby a concentrated uranyl nitrate solution with urea and ammonium nitrate as additives is dispersed horizontally into droplets that are hardened by external gelation. The process is very simple and consists of only a few steps, since no organic thickener is necessary and only aqueous solutions are used. The equipment, which has been developed for the special needs of the refabrication of 233U, has a throughput of ∼0.7 kgU/h.