Nuclear Techniques ›› 2019, Vol. 42 ›› Issue (11): 110602-110602.doi: 10.11889/j.0253-3219.2019.hjs.42.110602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

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

Bin DENG1,2,3,Jingen CHEN1,2,3(),Long HE1,2,3,Shaopeng XIA1,2,3,Chenggang YU1,2,Xiangzhou CAI1,2,3()   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2. Innovative Academies in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China
    3. University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2019-08-26 Revised:2019-09-20 Online:2019-11-10 Published:2019-11-18
  • Contact: Jingen CHEN,Xiangzhou CAI;
  • About author:DENG Bin, male, born in 1995, graduated from University of South China in 2017, master student, major in nuclear science and engineering
  • Supported by:
    Strategic Priority Research Program of Chinese Academy of Sciences(XDA02010000);the Frontier Science Key Program of Chinese Academy of Sciences(QYZDY-SSW-JSC016);National Natural Science Foundation of China(91326201)

Abstract: 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).


This work aims to develop and verify coupled code for steady-state neutronics and thermal-hydraulics for the MSFR.


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 neutonics 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.


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.


This coupled code can provide reliable results for the steady-state neutronics and thermal-hydraulics coupling of MSFR.

Key words: OpenMC, OpenFOAM, Molten salt fast reactor, Neutronics and thermal-hydraulics coupling

CLC Number: 

  • TL334