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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.
Tseelmaa Byambaakhuu, Dean Wang, Sicong Xiao
Nuclear Science and Engineering | Volume 192 | Number 2 | November 2018 | Pages 208-217
Technical Paper | doi.org/10.1080/00295639.2018.1499338
Articles are hosted by Taylor and Francis Online.
We present a local adaptive diffusion synthetic acceleration (DSA) method for neutron transport calculations. This new DSA method, called DG-DSA, solves the diffusion equation on a coarse mesh using the interior penalty discontinuous Galerkin (DG) methods. We investigate various numerical aspects of the DG-DSA method such as convergence performance and local adaptation. We demonstrate that our DG-DSA method can effectively and efficiently accelerate transport source iterations.