Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1707235 | Applied Mathematical Modelling | 2007 | 7 Pages |
Abstract
In this paper, we describe a new scattering kernel and general theoretical scheme for the evolution of the discrete and continuum eigenvalue spectrum in one-dimensional slab geometry neutron transport equation. Firstly, some useful properties of the Legendre polynomials which revealed during the definition of the new scattering kernel are discussed. By using the scattering kernel in one-dimensional neutron transport equation we obtained an integral equation for angular part of the angular flux. For the solution of this integral equation and eigenvalue equations, some comments are given.
Related Topics
Physical Sciences and Engineering
Engineering
Computational Mechanics
Authors
Fikret Anli, Süleyman Gungor,