Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (7): 70602-070602.doi: 10.11889/j.0253-3219.2018.hjs.41.070602

• NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH • Previous Articles     Next Articles

Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel

PENG Yipeng1,2,3, YU Chenggang1,2, CUI Deyang1,2, XIA Shaopeng1,2,3, ZHU Fan1,2,3, 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:2017-12-20 Revised:2017-12-20 Online:2018-07-10 Published:2018-07-07
  • Supported by:
    Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02010000), National Natural Science Foundation of China (No.91326201), Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)

Abstract: [Background] Compared with the molten fluoride salt reactor, the molten chloride salt fast reactor (MCFR) has outstanding advantages in terms of transuranics (TRU) solubility, neutron spectrum and melting point, so it is very crucial to study neutron performances of the MCFR to evaluate its feasibility. [Purpose] This study aims to optimize the composition and reprocessing method of the molten salt to enhance the breeding and burnup performance of MCFR. [Methods] Based on the molten salt reactor reprocessing sequence (MSR-RS), the effect of different carrier salt and starting fuel on burnup performance are analyzed and the composition of molten salt is optimized. Then, off-line batch reprocessing and on-line continuous reprocessing are introduced to improve burnup performance. [Results] After a series of optimization, the burnup-time is extended to 31 a, the burnup level is increased to 210GW·d·t-1, the production of 233U is 8300 kg, and finally 12000 kg of TRU is consumed corresponding to transmutation rate of 62.1%. [Conclusion] NaCl is a more suitable carrier salt for MCFR, and minor actinides (MA) in the TRU also helps to improve the breeding performance. Batch reprocessing can not only achieve great burnup performance but also reduces the requirement for the reprocessing system.

Key words: MCFR, Thorium uranium fuel cycle, Burnup

CLC Number: 

  • TL99