Solution of the neutron transport problem with anisotropic scattering in cylindrical geometry by the decomposition method |
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| Authors: | G.A. Gonç alves,S.Q. Bogado Leite,M.T. de Vilhena |
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| Affiliation: | 1. UFRGS, Departamento de Engenharia Nuclear, Av. Osvaldo Aranha 99, 4° andar, Porto Alegre, RS 90046-900, Brazil;2. Comissão Nacional de Energia Nuclear, Coordenação Geral de Reatores e Ciclo do Combustível, Rua General Severiano, 90, Rio de Janeiro, RJ 22294-900, Brazil;3. UFRGS, Departamento de Matemática Aplicada, Av. Bento Gonçalves, 9500, Porto Alegre, RS 91509-900, Brazil |
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| Abstract: | 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 FN method. |
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