Solution of the neutron transport problem with anisotropic scattering in cylindrical geometry by the decomposition method

被引：3
|
作者：
Goncalves, G. A. [2 ]
Leite, S. Q. Bogado [1 ]
de Vilhena, M. T. [3 ]
机构：
[1] Comissao Nacl Energia Nucl, Coordenacao Geral Reatores & Ciclo Combustivel, BR-22294900 Rio De Janeiro, Brazil
[2] Univ Fed Rio Grande do Sul, Dept Nucl Engn, BR-90046900 Porto Alegre, RS, Brazil
[3] Univ Fed Rio Grande do Sul, Dept Matemat Aplicada, BR-91509900 Porto Alegre, RS, Brazil
来源：
ANNALS OF NUCLEAR ENERGY | 2009年 / 36卷 / 01期
关键词：
Anisotropy;
D O I：
10.1016/j.anucene.2008.10.002
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
An analytical solution has been obtained for the one-speed stationary neutron transport problem, in an infinitely long cylinder with anisotropic scattering by the decomposition method. Series expansions of the angular flux distribution are proposed in terms of suitably constructed functions, recursively obtainable from the isotropic solution, to take into account anisotropy. As for the isotropic problem, an accurate closed-form solution was chosen for the problem with internal source and constant incident radiation, obtained from an integral transformation technique and the F-N method. (c) 2008 Elsevier Ltd. All rights reserved.
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页码：98 / 102
页数：5
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