In this work, a combination of forward and backward scattering is studied for the numerical solution of one-dimensional neutron transport problems in a finite homogeneons slab and sphere. The scattering of the neutron...
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In this work, a combination of forward and backward scattering is studied for the numerical solution of one-dimensional neutron transport problems in a finite homogeneons slab and sphere. The scattering of the neutrons is assumed to be anisotropic for the slab and isotropic for the spherical geometry. Numerical solutions are carried out by using both the spectral Green's functiori (SGF) and the diamond-difference (dd) methods to check the accuracy of the results. Calculated numerical results of cell-edge scalar fluxes are presented in the tables.
A GPU-based three-dimensional (3D) neutron transport code, named ThorMOC, is developed in this work. A GPU-parallelized transport sweeping algorithm based on a planar method of characteristics (MOC) is implemented in ...
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A GPU-based three-dimensional (3D) neutron transport code, named ThorMOC, is developed in this work. A GPU-parallelized transport sweeping algorithm based on a planar method of characteristics (MOC) is implemented in ThorMOC and a two-level coarse mesh finite difference (CMFD) method is used to accelerate the convergence of the MOC transport solution. To reduce the memory burden of 3D calculation, the transport sweeping algorithm is improved by azimuthal angle decomposition. This developed ThorMOC code is verified by a Takeda benchmark and a C5G7 3D extension benchmark, and the performance of the azimuthal angle decomposition algorithm is evaluated by the whole core calculation of a C5G7 hexagonal benchmark. The numerical results obtained from ThorMOC show a good agreement with those from the Monte Carlo code OpenMC. Besides, the azimuthal angle decomposition algorithm can reduce the GPU storage requirement by more than 40% for the C5G7 hexagonal benchmark. (c) 2022 Elsevier Ltd. All rights reserved.
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