THE NUMERICAL-ANALYSIS OF EIGENVALUE PROBLEM SOLUTIONS IN THE MULTIGROUP NEUTRON DIFFUSION-THEORY

The main goal of this paper is to present a general global-outer-inner iteration strategy for solving the discrete form of multidimensional neutron diffusion equations equivalent mathematically to an eigenvalue problem, The presented matrix formalism allows us to visualize explic itly how the used matrix splitting influences the matrix structure in an eigenvalue problem to be solved as well as the interdependence betw een inner and outer iterations within global iterations. Particular it erative strategies are illustrated by numerical results obtained for s everal reactor problems. (C) 1998 Elsevier Science Ltd.