Development And Application Of Neutronics-thermal Hydraulics Coupling Interface For CFETR Integration Design Platform

China Fusion Engineering Test Reactor(CFETR)is a superconducting tokamak which is under conceptual design.The missions of CFETR are achieving 50?200MW fusion power,steady-state burning plasma operation with the duty circle between 0.3 and 0.5.Besides,the Tritium Breeding Ratio of CFETR should be greater than 1 to achieve the tritium self-sustained and demonstrate the feasibility of fusion.An integration design platform is under development for CFETR to improve the efficiency and self-consistency of device design.It mainly consists of a physical design platform and an engineering design platform.The engineering platform includes various modules,such as magnet design module,divertor design module,vacuum vessel design module,neutronics interface module.Providing post-processing of analysis results is one of the neutronics module's objectives.In addition,it should provide necessary parameter and heating data for other modules.In the modules' design,Computational Fluid Dynamics(CFD)software is used to perform the thermal-hydraulic analysis of the fusion in-vessel components,such as ANSYS CFX and Fluent.In the thermal-hydraulic calculations,nuclear heating is a necessary source term.Generally,the nuclear heating source comes from neutronics calculations,which are widely performed by MCNP.On one hand CFD codes cannot recognize the output files of MCNP which contains the heating information,one the other hand it's inefficient and unrealistic to hand thousands of data in the heating profiles manually.In this paper,based on the CFETR integrated engineering design platform,a neutronics-thermal hydraulics coupling interface is developed.The coupling interface provides post-processing of heating profiles from MCNP,and it also provide the data exchange between MCNP and CFD code by two different interpolation methods:element-to-element mapping method and point-to-point mapping method.For verification purposes,thermal-hydraulic analysis based on breeder unit of the Helium Cooled Pebble Breeder blanket(HCPB)for CFETR was performed by CFX.Results of the thermal-hydraulic analysis proved the reliability of the coupling interface.Finally,the coupling interface was applied to the fluid structure interaction analysis of HCPB blanket with high-fidelity three-dimensional heating data.The analysis results provide support for the design of HCPB blanket.