Solution of the Neutron Transport Equation in R-Z and X-Y-Z Geometries by the Discrete Ordinates Method

The description of methods and corresponding codes for solving the multigroup transport equation in axially symmetric R-Z geometry (KINRZ code) and in rectangular three-dimensional X-Y-Z geometry (KINXYZ code) is presented. Program implementation is performed in the framework of the 'Reactor' package. The results of code testing are presented on widely used benchmarks.