Neutron Transport with Anisotropic Scattering
- 1 December 1961
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 11 (4) , 415-427
- https://doi.org/10.13182/nse61-1
Abstract
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.Keywords
This publication has 3 references indexed in Scilit:
- Elementary solutions of the transport equation and their applicationsAnnals of Physics, 1960
- Transfer Problems and the Reciprocity PrincipleReviews of Modern Physics, 1957
- On the spectrum of an unsymmetric operator arising in the transport theory of neutronsCommunications on Pure and Applied Mathematics, 1955