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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.










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