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A multi group finite-element solution of the neutron transport equation—II: R- Z geometry

Authors
Journal
Annals of Nuclear Energy
0306-4549
Publisher
Elsevier
Publication Date
Volume
12
Issue
5
Identifiers
DOI: 10.1016/0306-4549(85)90105-7
Disciplines
  • Mathematics

Abstract

Abstract The extension of a variational finite-element method of solving the neutron transport equation, to include multigroup-energy dependence in R- Z geometry, is evaluated. The method is implemented in a computer program called felicit. The solutions obtained by means of felicit to a number of axisymmetric test problems are given in numerous tables and graphs. A comparison is made between felicit, exact solutions and solutions obtained by other transport techniques. The ability of the method to handle problems characterized by difficult geometries is demonstrated; in particular by considering a fixed-source problem in a model Tokamak configuration.

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