Abstract
The neutron diffusion equation is defined based on the User Defined Function (UDF) and the User Defined Scalar (UDS) functions of the FLUENT. The neutron diffusion equation is solved iteratively by using the solver of the FLUENT with the Finite Volume Method (FVM). At the same time, the mass, momentum and energy equations are solved iteratively. At each iteration, the power distribution (flux distribution) obtained by the iteration of the neutron diffusion equation is transferred to the thermal-hydraulics calculation and is used as the heat source term. At the same time, the temperature distribution obtained from the thermal-hydraulics calculation is transferred to the neutron diffusion calculation and the macroscopic cross sections of the materials are corrected to realize the coupling calculation of the neutron diffusion and the thermal-hydraulics under the same solver of the FLUENT without needing to develop the interface program and the computational cost is saved. 2D-TWIGL benchmark problem is calculated by the FLUENT solver to verify the feasibility of this method to solve neutron diffusion equation. Through the modeling and calculation of the 5 × 5 PWR assembly model, the calculation results are compared with the results of other programs to verify the feasibility of the coupling method and the correctness of data transfer. Then this coupling method is applied to calculate the hot assembly of a modular lead-cooled fast reactor (M2LFR-1000) to verify that the thermal-hydraulics characteristics (the maximum fuel temperature and the maximum cladding outer surface temperature) are all within the corresponding thermal-hydraulics design limits.
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