Half-Space Multigroup Transport Theory
- 1 December 1969
- journal article
- Published by AIP Publishing in Journal of Mathematical Physics
- Vol. 10 (12) , 2220-2226
- https://doi.org/10.1063/1.1664827
Abstract
A method for solving various half-space multigroup transport problems for the case of a symmetric transfer matrix is explained. This method is based on the full-range completeness and orthogonality properties of the infinite-medium eigenfunctions. First, the albedo problem is considered. A system of Fredholm integral equations is derived for the emergent distribution of the albedo problem, and it is shown that this system has a unique solution. Then, by using the full-range eigenfunction completeness, the inside angular distribution is obtained from the emergent distribution. Finally, the Milne problem and the half-space Green's function problem are solved in terms of the emergent distribution of the albedo problem and the infinite-medium eigenfunctions.Keywords
This publication has 6 references indexed in Scilit:
- Multigroup Treatment of Neutron Transport in Plane GeometryNuclear Science and Engineering, 1968
- Two-group transport theoryJournal of Nuclear Energy, 1967
- Radiative Transfer. IIJournal of Mathematical Physics, 1966
- Energy-Dependent Neutron Transport Theory in Plane Geometry II. Eigenfunctions and Full-Range CompletenessNuclear Science and Engineering, 1966
- An exact solution of equations of radiative transfer for Local Thermodynamic Equilibrium in the non-gray case. Picket fence approximationAnnals of Physics, 1966
- Two-group approach in neutron transport theory in plane geometryAnnals of Physics, 1961