Abstract
The paper presents algorithm of solving neutron diffusion equation in three-dimensional space based on multiple application of alternating direction implicit method. The point of the method is to reduce solving of multidiagonal systems of equations to solving of few three diagonal systems in iterative processes. Diffusion code CriMR that uses this algorithm implemented for triangular mesh is described. Results of initial tests of the code are also presented (comparison of parameters of three different homogenized cores of BN-600 calculated by CriMR with ones of MCU-PTR).
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