Neutronics-thermal hydraulics coupling module for CFETR integration design platform

[Background] The China fusion engineering test reactor (CFETR) under development, mainly consists of a physical design platform and an engineering design platform, and the latter includes various modules. In the design of the modules, computational fluid dynamics (CFD) software is used for thermal-hydraulic analysis of the fusion in-vessel components of which the nuclear heating is a necessary source term generated from neutronics calculations of Monte Carlo N particle transport code (MCNP). [Purpose] This study aims to transfer the 3D nuclear heating profiles from MCNP to CFD software and develop neutronics-thermal hydraulics coupling module for CFETR integration design platform. [Methods] The 3D nuclear heating profiles were processed by two different interpolation methods: element-to-element mapping method and point-to-point mapping method, and the 1D nuclear heating profiles were also processed for comparison. Thermal-hydraulic analysis based on breeder unit of the helium cooled ceramic breeder blanket (HCCB) for CFETR was performed on ANSYS CFX for verification. The total interpolated nuclear heating, heating distributions and temperature distributions were compared in detail according to the CFX simulation results. [Results] Comparison results showed that all schemes satisfied the conservation of nuclear heating with appropriate mesh. Element-to-element mapping method and point-to-point mapping method differs in the heating peak value due to the different interpolation method. [Conclusion] The neutronics-thermal hydraulics coupling module proposed in this paper possesses high reliability for CFETR integration design platform. (authors)