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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.
S. Santandrea, R. Sanchez, P. Mosca
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 23-40
Technical Paper | doi.org/10.13182/NSE07-69
Articles are hosted by Taylor and Francis Online.
The method of characteristics (MOC) in unstructured meshes has become a standard for reactor physics applications. One of the major drawbacks of the MOC is the difficulty to implement higher-order integration schemes to improve spatial convergence. In this paper we present a high-order MOC spatial discretization that uses linear interpolation on surface values for the collision source. This conservative linear surface (CLS) scheme exhibits parabolic convergence with the mesh size but lacks positivity. Numerical results for the well-known Stepanek benchmark and for more realistic boiling water reactor assemblies show CLS faster convergence over the standard step characteristics scheme. A generalization of the synthetic DPN acceleration scheme provides an efficient method to accelerate the internal transport iterations.