Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (9): 90602-090602.doi: 10.11889/j.0253-3219.2016.hjs.39.090602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Design of fuel assembly for molten-salt-cooled reactors

XUE Chun1,2, ZHANG Haiqing1, ZHU Zhiyong1, LIN Jun1   

  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:2016-05-27 Revised:2016-07-19 Online:2016-09-10 Published:2016-09-09
  • Supported by:

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


Background: Molten salt reactor(MSR),a fourth generation reactor,possesses good economy and inherent safety properties.By using the fuel assembly in molten-salt-cooled reactor,it is expected that the fuel load and release can be easier and reliable,which is similar to that widely used in LWR(Light Water Reactor).Purpose: Based on spherical TRISO(Tristructural Isotropic)coated particle fuel elements,this study aims to design a fuel assembly model for the high-temperature molten-salt-cooled reactor.Methods: The MCNP(A Monte Carlo N-Particle Transport Code)is employed to investigate the feasibility and behavior of the fuel assembly by analyzing the infinite multiplication factorKinf,the reactivity temperature coefficient(RTC)and the void reactivity(VR)of the FLiBe coolant as a function of the composition,density and wall thickness of the assembly material,the TRISO coated particles packing factor and the enrichment of7Li in FLiBe salt.Results and Conclusion: The results show that carbon-based materials are significantly better than silicon-carbide-based materials for fuel assembly.Increasing the TRISO packing factor and enrichment of7Li helps to improve neutron economy and security properties of the reactor.

Key words: MSR, Fuel assembly, TRISO particle, Reactivity temperature coefficient

CLC Number: 

  • TL32