A New Nodal SN Transport Method for Three-Dimensional Hexagonal Geometry.
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概要
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A new nodal SN transport method has been developed so as to perform accurate transport calculations in three-dimensional (3-D) hexagonal geometry. In the present method the neutron angular distributions of intra-node fluxes and transverse-leakage are represented using the S<SUB>N</SUB> quadrature set, and the spatial distribution of neutron source is approximated by a quadratic polynomial expansion. Additionally, the authors have applied the nodal-equivalent finite difference algorithm to 3-D hexagonal geometry in order to establish a stable and efficient iterative scheme, <BR>The present method has been applied to a fast reactor benchmark problem. The results of the present method agree well with those of a Monte Carlo method, the difference in k<SUB>eff</SUB> being less than 0.05%Δk. This shows high accuracy of the present method.
- 一般社団法人 日本原子力学会の論文
著者
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Takeda Toshikazu
Department of Nuclear Energy, Graduate School of Engineering, Osaka University
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IKEDA Hideaki
Department of Nuclear Engineering, Faculty of Engineering, Osaka University
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