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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.
H. S. Bailey, Y. S. Lu
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 76-82
Technical Paper | Reactor | doi.org/10.13182/NT79-A32239
Articles are hosted by Taylor and Francis Online.
A study of various core designs was conducted to investigate design features pertaining to the preclusion of energetic hypothetical core disruptive accidents. The design data and core layouts for different designs are described. A summary of the nuclear performance predicted for several typical low sodium void worth cores is presented. It appears that the tightly coupled heterogeneous core configuration offers a substantial reduction in prompt void worth and flux level at the expense of greater inventory, large flux gradients, and large changes in internal blanket power over the operating cycle.