Two-dimensional kinetic equation calculation of a reactor by the finite element method

In this paper, the authors describe the triangular mesh algorithm for the two-dimensional multigroup neutron transport equation calculation of a nuclear reactor with hexagonal fuel elements by the method of finite elements. It is assumed that the neutron flux and source within the triangular cells have the form of a plane. ALGOL-60-code ''Tri'', which realizes this algorithm for computer BESM-6, is presented. The described method is illustrated by the example of a fast physical assembly calculation