American Nuclear Society

Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 41 / Number 1

A Numerical Method for the Solution of Three-Dimensional Neutron-Transport Problems

M. R. Wagner, D. A. Sargis, S. C. Cohen

Nuclear Science and Engineering

Volume 41 / Number 1 / July 1970 / Pages 14-21


Member Price:$27.00
Member Savings:$3.00

A low-order discrete ordinates model for the solution of a certain class of three-dimensional neutron-transport problems is described. The method can be applied to cuboidal configurations with a region structure that allows the use of constant mesh spacings in each of the three coordinate directions. The angular flux distribution in a unit mesh cell is described in terms of discrete directions connecting the midpoints of 14 neighbor cells. A three-dimensional multigroup discrete ordinates code 3DT has been written for x, y, z-geometry which allows calculation of various configurations for small critical assemblies with computing speed far surpassing Monte Carlo techniques. The computed results for individual fuel-block reactivity worths of the fast thermionic critical experiment of Gulf General Atomic are in most cases in excellent agreement with experiment.

Questions or comments about the site? Contact the ANS Webmaster.