Application of analytic nodal method to CANDU space-time kinetics calculations

In this paper the analytic nodal method is used for the solution of the 2D-neutron diffusion equations both for one and two energy groups. For one energy group calculations, different transverse leakage approximations are presented. A new model, named transverse leakage proportional with flux is proposed. For two energy group calculation only the flat transverse leakage approximations are employed. The models are applied and tested for CANDU 600 reactor case, and accurate static and dynamic results in very short computing times were obtained. Also, a flux reconstruction method is presented. The method starts with the averaged nodal fluxes calculated with nodal analytical method. The flux reconstruction method is specific for CANDU reactors. (authors)