An Approximation to the Solution of the Transport Equation and Calculation of Diffusion Lengths in Multiplying Media

Abstract 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.