A PROGRAM FOR SOLVING A 2D STATIONARY TRANSPORT EQUATION
P. A. Avdeev, V. A. Shumilin VANT. Ser. Metodiki i Programmy Chislennogo Resheniya Zadach Matematicheskoy Fiziki 1984. Вып.1. С. 4548.
A technique and a FORTRANsubroutine are described for a numerical solution of a stationary onegroup 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 FORTRANprogram.
