Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (2): 20602-020602.doi: 10.11889/j.0253-3219.2017.hjs.40.020602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor

JING Jianping1, JIA Bin1, LEI Lei1, BI Jinsheng1, ZUO Jiaxu1, LIU Yaning2, ZHANG Chunming1, ZHANG Dalin3   

  1. 1. Nuclear and Radiation Safety Center, Beijing 100082, China;
    2. State Key Laboratory of Multiphase Complex Systems, Institute of Process Engineering, Chinese Academy of Sciences, Beijing 100190, China;
    3. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
  • Received:2016-11-21 Revised:2016-12-13 Online:2017-02-10 Published:2017-01-24
  • Supported by:

    Supported by Strategic Priority Program of Chinese Academy of Sciences (No.XDA02050500), National Natural Science Foundation of China (No.11505076, No.21306201)


Background: Thorium-based molten salt reactor nuclear power system project is one of the leading science and technology projects of Chinese Academy of Sciences, its strategic goal is to develop the fourth generation fission reactor nuclear power system. The core of solid fuel molten salt reactor is constructed of the random pileup of fuel graphite balls, which brings difficulties and uncertainties in the establishment of the pebble bed model for simulation analysis. Purpose: This study aims to analyze the influence of two modes of fuel ball arrangement on the core flow and heat transfer in the molten salt reactor, which are face centered cubic (FCC) and body centered cubic (BCC) arrangement mode. Methods: Based on the computational fluid dynamics (CFD) program, two computational models based on the FCC and BCC arrangement modes are established respectively. The re-normalization group (RNG) k-ε turbulence model is selected with constant velocity and temperature as the inlet boundary conditions and constant pressure as the outlet boundary condition whilst the gauge pressure is assumed to be zero. Results: Compared to the BCC arrangement mode, the streamline under the FCC arrangement mode is more complex, the flow pressure drop is larger, the fuel ball surface temperature distribution is more uniform, and the hot spot temperature is lower. Under the FCC arrangement mode, the maximum temperature of the ball center is 1153 K, the total pressure drop is 1323 Pa; under the BCC arrangement mode, the maximum temperature of the ball center is 1155 K, the total pressure drop is 574 Pa. Conclusion: The streamlines under the FCC arrangement mode are periodically curved and the streamlines under the BCC arrangement mode are generally straight. Under FCC arrangement mode, the surface temperature distribution of a single intermediate fuel ball is more uniform and the hot spot temperature is lower, but the pressure drop from the bottom of the fuel ball to the top is larger than that of BCC arrangement mode.

Key words: Thorium Molten Salt Reactor-Solid Fuel (TMSR-SF), CFD, Arrangement mode, Flow and heat transfer

CLC Number: 

  • TL99