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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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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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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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AC loss and contact resistance of different CICC cable patterns: Experiments and numerical modeling
/ Anvar, V A (Twente U., Enschede ; Wollongong U.) ; Qin, J (Hefei, Inst. Plasma Phys.) ; Wu, Y (Hefei, Inst. Plasma Phys.) ; Bagni, T (Twente U., Enschede) ; Devred, A (CERN) ; Haugan, T J (Aero. Syst. Div., Wright-Patt. AFB) ; Hossain, M S A (Wollongong U. ; Queensland U.) ; Zhou, C (Twente U., Enschede ; Hefei, Inst. Plasma Phys.) ; Nijhuis, A (Twente U., Enschede)
For upcoming nuclear fusion energy reactors, like the China Fusion Engineering Test Reactor (CFETR) and EU-DEMO, the superconducting Cable-In-Conduit Conductors (CICC) are in the design phase, and the operatingconditions like electromagnetic forces can be higher than in previous devices like ITER. The prototype con-ductors for the Central Solenoid (CS) coils in the CFETR, for example, are designed to produce a peakfield of19.9 T and are expected to be made of high current density Nb3Sn strands. [...]
2020 - 11 p.
- Published in : Fusion Eng. Des. 161 (2020) 111898
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Local plastic deformation effects on the critical current of high-J$_{c}$ Nb$_{3}$Sn strands under uniaxial strain
/ Liu, Yunhao (Hefei, CUST) ; Sun, Yi (Hefei, CUST) ; Gao, Peng (Hefei, CUST) ; Nijhuis, Arend (Twente U., Enschede) ; Devred, Arnaud (CERN) ; Guo, Zichuan (Hefei, CUST) ; Zhu, Huajin (Guangxi Normal U.) ; Xu, Peng (Hefei, CUST) ; Shi, Yi (Hefei, CUST) ; Liu, Fang (Hefei, CUST)
In order to meet the target operating parameters of the toroidal field coils (TFCs) for the next-generation Chinese compact burning plasma tokamak, high critical current density (J$_{c}$) Nb$_{3}$Sn strand will be applied to the high-field winding-package of the TFC. To improve the transverse stiffness of the cable in withstanding the huge Lorentz force and avoiding conductor performance degradation, the short-twist-pitch and copper-wound-strand cable patterns were taken into consideration. [...]
2024 - 7 p.
- Published in : Supercond. Sci. Technol. 37 (2024) 115009
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Qualification of the Manufacturing Procedures of the ITER Correction Coils
/ Libeyre, P (Euratom, St. Paul Lez Durance) ; Cormany, C (Euratom, St. Paul Lez Durance) ; Dolgetta, N (Euratom, St. Paul Lez Durance) ; Gaxiola, E (Euratom, St. Paul Lez Durance) ; Ilyin, Y (Euratom, St. Paul Lez Durance) ; Mitchell, N (Euratom, St. Paul Lez Durance) ; Simon, F (Euratom, St. Paul Lez Durance) ; Evans, D (Euratom, St. Paul Lez Durance) ; Sgobba, S (CERN) ; Langeslag, S A E (CERN) et al.
The system of correction coils (CC) is a component of the ITER magnet system, required to correct toroidal asymmetries and reduce error magnetic fields detrimental for physical processes in the plasma. It includes 18 coils, inserted in between toroidal field coils and poloidal field coils and split into 3 sets of 6 coils each: bottom correction coils (BCC), side correction coils (SCC), and top correction coils (TCC). [...]
2017 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 27 (2017) 4201405
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