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Neutron Transport with Anisotropic Scattering

Janusz R. Mika

Nuclear Science and Engineering

Volume 11 / Number 4 / December 1961 / Pages 415-427


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The general procedure of solving the one-velocity Boltzmann equation in the case of plane geometry is presented. It is assumed that the scattering function can be expanded into the finite series of Legendre polynomials. The complete set of eigenfunctions of the Boltzmann equation is found. The orthogonality and completeness of the eigenfunctions are proved. By way of illustration, solutions of some basic problems of neutron diffusion are given.

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