Development and verification of a coupled code of steady-state neutronics and thermal-hydraulics for molten salt fast reactor

[Background] There is a strong coupling between the neutronics and thermal-hydraulics in the non-moderated can-type core of molten salt fast reactor (MSFR). [Purpose] This work aims to develop and verify coupled code for steady-state neutronics and thermal-hydraulics for the MSFR. [Methods] The coupling code was developed using python programming language to exchange the power distribution, fuel salt temperature and density distributions between OpenMC (Monte Carlo particle transport simulation code) and OpenFOAM (computational fluid dynamics software). Based on the coupling code, a benchmark model of MSFR was established, and the effects of the number of neutronics region division and the different initial conditions on the k_eff, fuel salt velocity and temperature distributions were studied. Finally, the simulation results were compared with the reference results of MSFR. [Results] The three-dimensional power distribution, neutron flux distribution, fuel salt velocity field and temperature field distributions can be obtained by using this coupled code. The benchmark of MSFR shows that different initial conditions have no effect on k_eff, and an alternative number and scheme of neutronics region division are recommended. The simulation results keep a good agreement with the reference results of MSFR. [Conclusions] This coupled code can provide reliable results for the steady-state neutronics and thermal-hydraulics coupling of MSFR. (authors)