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Home / Publications / Journals / Nuclear Science and Engineering / Volume 38 / Number 2

Anisotropic Multigroup Transport Theory

J. Kenneth Shultis

Nuclear Science and Engineering / Volume 38 / Number 2 / November 1969 / Pages 83-93

Technical Paper / dx.doi.org/10.13182/NSE69-A19512

A method for solving various infinite medium and half-space multigroup transport problems with anisotropic transfer is presented. A set of eigensolutions for the homogeneous multigroup equations is obtained and is shown to have “full-range” completeness and orthogonality properties. These properties then can be used to solve for the infinite medium Green's function. Half-space problems are solved in two distinct steps. First, the emergent distribution is calculated. Then, application of the full-range completeness property gives the complete solution everywhere in the half-space. The success of this method implies that the eigensolutions also possess a “half-range” completeness property.