Refinement of the method of homogenization of a heterogeneous reactor

The foundations of a method are outlined which yields a very (as you like) precise finite difference analog of the heterogeneous reactor kinetics equation. Starting approximations of the method coincide with those used in the homogenzation method. Within the framework of the multigroup approximation transverse neutron diffusion is considered in one-dimensional (infinite plates) and two-dimensional (triangular) reactor lattices. As an example there has been calculated power distribution in a WWER type reactor fuel assembly. The proposed refinement of finite difference equations has been shown to be noticeable for the power distribution near strong inhomogeneities of the lattice