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Manufacture and performance test result of a 95 kA-class Nb-Ti cable-in-conduit conductor for the low field winding-package of CFETR-TF coil / Dai, Chao (Hefei, Inst. Plasma Phys.) ; Wu, Yu (Hefei, Inst. Plasma Phys.) ; Sedlak, Kamil (LPHE, Lausanne) ; Bajas, Hugo (LPHE, Lausanne) ; Nijhuis, Arend (Twente U., Enschede) ; Bruzzone, Pierluigi (LPHE, Lausanne) ; Devred, Arnaud (CERN) ; Qin, Jinggang (Hefei, Inst. Plasma Phys.) ; Liu, Yunhao (Hefei, CUST) ; Xue, Tianjun (Showa Wire Cable, Kawasaki) et al.
The engineering design of the CFETR TF prototype coil and conductors has been completed. The wind-package (WP) of the coil is graded into three regions based on the magnetic field distribution for saving cost. [...]
2023 - 8 p. - Published in : Physica C 606 (2023) 1354212

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Performance of the Cable-in-Conduit Conductors for Super-X Test Facility / Dai, Chao (Hefei, Inst. Plasma Phys.) ; Wu, Yu (Hefei, Inst. Plasma Phys.) ; Shi, Yi (Hefei, Inst. Plasma Phys.) ; Sedlak, Kamil (Ecole Polytechnique, Lausanne) ; Bajas, Hugo (Ecole Polytechnique, Lausanne) ; Nijuis, Arend (Twente U., Enschede) ; Hao, Qiangwang (Hefei, Inst. Plasma Phys.) ; Han, Houxiang (Hefei, Inst. Plasma Phys.) ; Liu, YunHao (USTC, Hefei) ; Devred, Arnaud (CERN) et al.
Following the conceptual design, the engineering design of the dc magnet and cable-in-conduit conductor (CICC) for the Super-X test facility has been done in 2021. Totally three types of conductors with different structures were designed for the three pairs of coils in the dc magnet, respectively. [...]
2023 - 5 p. - Published in : IEEE Trans. Appl. Supercond. 33 (2023) 9500105

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Performance test and analysis of the first large-scale cable-in-conduit conductor with high $J$$_{c}$ Nb$_{3}$Sn strand for fusion reactor / Dai, Chao (Hefei, Inst. Plasma Phys.) ; Wu, Yu (Hefei, Inst. Plasma Phys.) ; Li, Jiangang (Hefei, Inst. Plasma Phys.) ; Guo, Zichuan (USTC, Hefei) ; Qin, Jinggang (Hefei, Inst. Plasma Phys.) ; Long, Feng (Hefei, Inst. Plasma Phys.) ; Nijhuis, Arend (Twente U. Tech., Enschede) ; Bruzzone, Pierluigi (PSI, Villigen) ; Stepanov, Boris (PSI, Villigen) ; Shi, Yi (Hefei, Inst. Plasma Phys.) et al.
The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. [...]
2021 - 10 p. - Published in : Nucl. Fusion 61 (2021) 036044

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Research on mechanical properties of high-performance cable-in-conduit conductors with different design / Guo, Zichuan (Hefei, CUST ; Hefei, Inst. Plasma Phys.) ; Dai, Chao (Hefei, Inst. Plasma Phys.) ; Qin, Jinggang (Hefei, Inst. Plasma Phys.) ; Zhou, Chao (Hefei, Inst. Plasma Phys.) ; Li, Jiangang (Hefei, Inst. Plasma Phys.) ; Yu, Wu (Hefei, Inst. Plasma Phys.) ; Liu, Fang (Hefei, Inst. Plasma Phys.) ; Yang, Dongsheng (Hefei, Inst. Plasma Phys.) ; Huang, Chuanjun (Beijing, Tech. Inst. Phys. Chem.) ; Li, Laifeng (Beijing, Tech. Inst. Phys. Chem.) et al.
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak fusion reactor under preliminary design, where the toroidal field (TF) coil has been designed to create a magnetic field of over 14.3 T. The TF conductors need to operate stably at 14.3 T, requiring the exclusion of conductor performance degradation from thermal and electromagnetic loading as much as possible. [...]
2020 - 13 p. - Published in : Supercond. Sci. Technol. 33 (2020) 045002

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