Various anisotropic scattering kernels are presented to solve the transport equation in multiplying media, and calculations are also performed for the isotropic scattering case and the non-multiplying medium to enable a meaningful comparison. Henyey–Greenstein-like scattering kernel is employed to model anisotropic scattering of neutrons. The effect of anisotropic scattering on the diffusion length of a multiplying slab is investigated using the Legendre polynomial expansion method. A comprehensive numerical analysis of diffusion lengths was performed to represent the fuel system in a nuclear reactor.
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Faruk Yaşa (2026) studied this question.
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