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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.
B. Merk, F. P. Weiß
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 152-174
Technical Paper | doi.org/10.13182/NSE163-152
Articles are hosted by Taylor and Francis Online.
This work presents the development of an analytical approximation solution for a space-time-dependent neutron transport problem in a one-dimensional system consisting of a homogenized medium with a central external source with Green's functions. The delayed neutron production is implemented in two additional timescales with the multiple-scale expansion method. Qualitative results for a given system are analyzed, and a detailed comparison of the developed analytical approximation solution with results gained by the point-kinetics equation and the time-dependent diffusion equation without separation of space and time is given.