Analytical Reconstruction of Monoenergetic Neutron Angular Flux in Non-multiplying Slabs Using Diffusion Synthetic Approximation

Abstract

The migration of neutrons inside material media with the probabilities of interactions of the neutrons with the atom nuclei of the media can be mathematically modeled by the first order form of the phase-space neutron transport equation. In this work we describe a synthetic method to solve analytically a simplified model of the one-speed slab-geometry neutron transport equation. In the present synthetic method, the simplifying physical assumption is the neutron diffusion theory, which is an accurate approximation for low absorbing media, away from structural boundaries and from localized fixed sources, where the neutron flux become highly anisotropic. Numerical results are given to illustrate the efficiency of the developed code.