Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (8): 80603-080603.doi: 10.11889/j.0253-3219.2017.hjs.40.080603

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Coupled neutronic and thermal-hydraulic analysis of TMSR-SF1 at steady state

CHEN Jiahao1,2, ZHANG Haiqing1, ZHU Zhiyong1   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
    2. University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2017-03-10 Revised:2017-06-06 Online:2017-08-10 Published:2017-08-11
  • Supported by:

    Supported by Strategic Priority Program of Chinese Academy of Sciences (No.XDA02030200)

Abstract:

Background: Neutronic and thermal-hydraulic simulations of advanced reactors can affect each other's results. Purpose:This study focuses on coupling neutronic and thermal-hydraulic simulations to achieve more accurate results for future developments of 10-MW solid-fueled thorium molten salt experimental reactor (TMSR-SF1). Methods: A program converting the MCNP (Monte Carlo N particle transport code) results to the spatial distribution of power density within the active region was created using C++ programming language. The spatial distribution data were loaded into the ANSYS Fluent in the form of user-defined function (UDF) to accomplish the coupling of the two simulation processes. In regards of TMSR-SF's original design parameters, the physical and thermal-hydraulic models of the whole core were established by using MCNP and ANSYS Fluent respectively. Results: The coupling method is feasible and can be used to obtain reliable results. The changes in coolant's temperature and velocity in the active region are dependent on the power density distribution. The changes in multiplication factor, power density and maximum of discrepancy in coolant temperature are 1.08%, 3.31% and 7.58 K, respectively. Conclusion: It is necessary to take the coupling effects of the reactor core into consideration in the design of associated reactor systems. In addition, the results confirm that the design parameters of the TMSR-SF1 are reasonable.

Key words: Fuel pebble, Thorium molten salt reactor, Neutronics and thermal-hydraulics coupling, Steady-state analysis

CLC Number: 

  • TL426