Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (8): 80601-080601.doi: 10.11889/j.0253-3219.2018.hjs.41.080601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Study of the neutronics performance of molten salt fuel in an accelerator driven subcritical reactor

ZHAO Xuechao1,2,3, CAI Xiangzhou1,2,3, CHEN Jingen1,2,3   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, 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:2018-03-16 Revised:2018-04-12 Online:2018-08-10 Published:2018-08-15
  • Supported by:
    Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02010000), Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)

Abstract: [Background] Accelerator-driven subcritical molten salt reactor (ADS-MSR) has many unique advantages and features for advanced nuclear fuel utilization.[Purpose] This study aims to analyze the influence of neutronics performance of the molten salt fuel in ADS.[Methods] In this work, the Monte Carlo N particle transport code (MCNP) program was employed to calculate the proton source efficiency, the neutron spectrum and the Th-U breeding in an accelerator driven subcritical molten salt reactor.[Results] Molten salt fuels will enhance the moderation to spallation neutrons and fission neutrons while improving the proton source efficiency. The moderating effect of molten salt reduces the Th-U breeding capability at the beginning of burnup, and the CR of FLi, FLiBe and oxide fuel were 1.023, 1.062 and 1.068 respectively. On the other side,with on-line refueling and fuel processing, the CR of FLi and FLiBe salt become higher than oxide fuel in the first year and 3rd year of the burnup, and can stabilize around 1.06 and 1.00 for a long period of time, respectively.[Conclusion] Compared to the oxide fuel, the FLi molten salt fuel has the better performance on Th-U breeding in an accelerator driven subcritical reactor.

Key words: Molten salt fuel, Proton efficiency, Th-U breeding, On-line processing

CLC Number: 

  • TL99