Three-Dimensional Multigroup Diffusion Code ANDEX Based on Nodal Method for Cartesian Geomry

摘要

An analytic polynomial nodal method using partial currents has been derived for the solu tion of multigroup neutron diffusion equations in three-dimensional (3-D) cartesian geometry. This method is characterized by expressing the source and leakage terms in an auxiliary 1-D diffusion equation by quadratic polynomials and solving it analytically. Based on this method, we have developed a 3-D multigroup diffusion code ANDEX, and applied to 2-D LWR and 3-D FBR models. The results of ken, power distributions and computing time have been compared with those of finite difference method calculations.