Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (10): 152 doi: 10.1007/s41365-017-0303-y

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Transition towards thorium fuel cycle in a molten salt reactor by using plutonium

De-Yang Cui 1,2,3 , Shao-Peng Xia 1,2,3 , Xiao-Xiao Li 1,2 , Xiang-Zhou Cai 1,2,3 , Jin-Gen Chen 1,2,3   

  1. 1 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2 CAS Innovative Academies in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China
    3 University of Chinese Academy of Sciences, Beijing 100049, China
  • Contact: Xiang-Zhou Cai E-mail:caixz@sinap.ac.cn
  • Supported by:

    This work was supported by the Chinese TMSR Strategic Pioneer Science and Technology Project (No. XDA02010000), the National Natural Science Foundation of China (No. 91326201) and the Frontier Science Key Program of the Chinese Academy of Sciences (No. QYZDY-SSW-JSC016).

PDF ShareIt Export Citation
De-Yang Cui, Shao-Peng Xia, Xiao-Xiao Li, Xiang-Zhou Cai, Jin-Gen Chen. Transition towards thorium fuel cycle in a molten salt reactor by using plutonium.Nuclear Science and Techniques, 2017, 28(10): 152     doi: 10.1007/s41365-017-0303-y

Abstract:

The molten salt reactor (MSR), as one of the Generation IV advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation resistance. The aim of this work is to provide and evaluate possible solutions to fissile 233U production and further the fuel transition to thorium fuel cycle in a thermal MSR by using plutonium partitioned from light water reactors spent fuel. By using an in-house developed tool, a breeding and burning (B&B) scenario is first introduced and analyzed from the aspects of the evolution of main nuclides, net 233U production, spectrum shift, and temperature feedback coefficient. It can be concluded that such a Th/Pu to Th=233U transition can be accomplished by employing a relatively fast fuel reprocessing with a cycle time less than 60 days. At the equilibrium state, the reactor can achieve a conversion ratio of about 0.996 for the 60-day reprocessing period (RP) case and about 1.047 for the 10-day RP case. The results also show that it is difficult to accomplish such a fuel transition with limited reprocessing (RP is 180 days), and the reactor operates as a converter and burns the plutonium with the help of thorium. Meanwhile, a prebreeding and burning (PB&B) scenario is also analyzed briefly with respect to the net 233U production and evolution of main nuclides. One can find that it is more efficient to produce 233U under this scenario, resulting in a double time varying from about 1.96 years for the 10-day RP case to about 6.15 years for the 180-day RP case.

Key words: Molten salt reactor, Thorium fuel cycle, Plutonium, Reprocessing