[1] JIANG Mianheng, XU Hongjie, DAI Zhimin. Advanced fission energy program-TMSR nuclear energy system[J]. Bulletin of Chinese Academy of Sciences, 27, 366-374(2012).

[2] LI Wenxin, LI Qingnuan. Molten salt reactor: a new source of innovation development for radiochemistry[J]. Journal of Nuclear and Radiochemistry, 38, 327-336(2016).

[3] XU Hongjie, DAI Zhimin, CAI Xiangzhou et al. Thorium-based molten salt reactor and comprehensive utilization of nuclear energy[J]. Modern Physics, 30, 25-34(2018).

[4] LI Qingnuan, ZHANG Lan, ZHOU Wei et al. Research progress on fuel cycle technology of thorium based molten salt reactor nuclear power system[C](2014).

[5] Lindauer R. Processing of the MSRE flush and fuel salts[R]. ORNL-TM-2578(1969).

[6] Rosenthal M W, Haubenreich P N, Briggs R B. The development status of molten-salt breeder reactors[R]. ORNL-4812(1972).

[7] Niu Y S, Sun L X, Fu H Y et al. Preliminary research on selective extraction of 99Mo from fuel salt for molten salt reactor[J]. Separation and Purification Technology, 345, 127424(2024).

[8] Sun L X, Niu Y S, Hu C W et al. Behavior and distribution of nuclides in the fluoride volatility process of uranium containing molten salt fuel[J]. Journal of Fluorine Chemistry, 261, 110016(2022).

[9] ZHENG Xiaoqiang, DOU Qiang, CHENG Ming et al. Study on removal of oxide from carrier salt in molten salt reactor by vacuum distillation[J]. Nuclear Techniques, 45, 040302(2022).

[10] FU Haiying, GENG Junxia, YANG Yang et al. Low pressure distillation technology of molten salt in spent fuel pyroprocessing field[J]. Nuclear Techniques, 41, 040001(2018).

[11] Benedict R, Goff M, Teske G et al. Progress in electrometallurgical treatment of spent nuclear fuel[J]. Journal of Nuclear Science and Technology, 39, 749-752(2002).

[12] Park H S, Chang H C, Kim K H et al. 3D simulation for the device arrangement and the remote accessibility analysis in a hot cell[J]. Transactions of the American Nuclear Society, 105, 897-898(2011).

[13] Park H S, Choi C H, Kim S H et al. Deployment analysis and remote accessibility verification for a maintenance task in a PRIDE digital mock-up[J]. Annals of Nuclear Energy, 38, 767-774(2011).

[14] WU Wenguang, SONG Changfei, CHEN Mingchi. Research and design of module supporting and rotary device in hot cell[J]. Nuclear Techniques, 36, 020602(2013).

[15] XIE Xiaolong, WANG Guangkai, TANG Qing et al. Assessment and expectation for overall design requirements of remote handling technologies for decommissioning of spent nuclear fuel reprocessing plant[J]. Nuclear Science and Engineering, 36, 398-403(2016).

[16] JIA Haopeng, TENG Lei, WANG Shuai et al. Research on efficient compound decontamination technology for decommissioning of highly radioactive hot cell[J]. Nuclear Power Engineering, 42, 193-196(2021).

[17] LIU Fang, LI Gaoliang, LUO Fangxiang et al. The first dissolution of real spent fuel in CRARL[R]. Annual Report of China Institute of Atomic Energy(2015).