An Improvement of the Transverse Leakage Treatment for the Nodal S_N Transport Calculation Method in Hexagonal-Z Geometry
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概要
- 論文の詳細を見る
To overcome the divergent behavior of the NSHEX code, a nodal S<SUB>N</SUB> code for hexagonal geometry, for some transport calculations, an improvement has been made in the calculation of the axial leakage. The axial leakage, previously calculated by using the quadratic transverse leakage approximation (QLA), is calculated by a new method of analytically treating the spatial distribution within a node, based on the axial homogeneity of the ordinary core. The verification tests were performed for the KNK-II model geometry of the NEACRP 3-D Neutron Transport Benchmarks and the large assembly-size KNK-II model. It is found that k<SUB>eff</SUB> values obtained by introducing the new method agree with the reference Monte Carlo calculation results within 0.1% Δk/k for the KNK-II model, although the QLA method did not converge for two cases. Furthemore the new method succeeded in calculations for the large assembly-size model, in which the QLA method failed for all cases. Thus the new method has been found accurate and convergence achieved for the cases in which the QLA method failed.
- 社団法人 日本原子力学会の論文
- 1996-08-25
著者
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Takeda Toshikazu
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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Sugino K
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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SUGINO Kazuteru
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
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Takeda Toshikazu
Department of Nuclear Energy, Graduate School of Engineering, Osaka University
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