Abstract: A mathematical nuclear CANada Deuterium Uranium (CANDU) reactor steady and transient modelling simulation is built to get the axial thermal power distribution. With a relatively small number of nodes (100-500 nodes) to present the core, based upon two energy group Neutron Diffusion Formulation and a typical spatial discretization, according to equivalence theory and homogeneous method, this is accomplished by properly defining the nuclear properties (absorption and fission cross sections, diffusion coefficient, etc.) characterizing each of the nodes finished. The 390 channels thermal power distribution is calculated under Linux language environment. The thermal power difference is within 5% error with IAEA database. The proposed modeling simulation can solve the large error and big redundant in comparison with the Flux-Volume-Weighted (FVW) method and Finite Difference Method (FDM), there is an important meaning for nuclear reactor fuel management research and optimization.

Key words: canada deuterium uranium (CANDU), equivalence theory, homogeneous parameters, nuclear reactor power, modelling