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 ›› 2020, Vol. 31 ›› Issue (4): 33 doi: 10.1007/s41365-020-0751-7


Feasibility of an innovative long-life molten chloride-cooled reactor

Ming Lin 1,2, Mao-Song Cheng 1, Zhi-Min Dai 1   

  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:2019-10-28 Revised:2020-02-16 Accepted:2020-02-17
  • Contact: Mao-Song Cheng
  • Supported by:
    This work is supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences (No. XD20191031).
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Ming Lin, Mao-Song Cheng, Zhi-Min Dai. Feasibility of an innovative long-life molten chloride-cooled reactor.Nuclear Science and Techniques, 2020, 31(4): 33     doi: 10.1007/s41365-020-0751-7

Abstract: Molten salt-cooled reactor is one of the six Gen-IV reactors with promising characteristics including safety, reliability, proliferation resistance, physical protection, economics, and sustainability. In this paper, a small innovative molten chloride-cooled fast reactor (MCCFR) with 30-year core and a target 120-MWt thermal power was presented. For its feasible study, neutronics, thermal-hydraulics, and radiation damage analysis were performed. The key design properties including kinetics parameters, reactivity swing, reactivity feedback coefficients, maximum accumulated displacement per atom (DPA) of reactor pressure vessel (RPV) and fuel cladding, and maximum coolant, cladding, and fuel temperatures were evaluated. The results showed the MCCFR could operate without refuelling for 30 years with overall negative reactivity feedback coefficients up the end of its life. During its 30-year life, the excess reactivity was well managed by constantly pulling out the control rods. The maximum accumulated DPA on RPV and fuel cladding were 8.92 dpa and 197.03 dpa, respectively, which are both below the design limits. Similarly, the maximum coolant, cladding and fuel center temperatures were all below the design limits during its entire lifetime. According to these results, the MCCFR core design with long life is feasible.

Key words: Molten salt-cooled reactor, Neutronics, Radiation damage, Thermal-hydraulics