A PROGRAM FOR SOLVING A 2-D STATIONARY TRANSPORT EQUATION

P. A. Avdeev, V. A. Shumilin
VANT. Ser. Metodiki i Programmy Chislennogo Resheniya Zadach Matematicheskoy Fiziki 1984. Вып.1. С. 45-48.

      A technique and a FORTRAN-subroutine are described for a numerical solution of a stationary one-group neutron transport problem assuming an axial symmetry. The subroutine calculates a new approximation and corresponding quasidiffusion coefficients using a predetermined neutron density approximation. The subroutine communicates with the external environment through parameters, so it may be easily included in any FORTRAN-program.

      The paper briefly describes a set of cataloged procedures written in the ES OS command language which were used to develop a sufficiently large program. These allow module text editing, its translation, link editing, and independent execution of modules. To use similar procedures for a new program development, they need to be modified and given different names.