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CERN Document Server 找到 5 筆記錄  檢索需時 0.72 秒. 
1.
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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2.
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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3.
Performance of first insert coil with REBCO CICC sub-size cable exceeding 6 kA at 21 T magnetic field / Zhou, Chao (Hefei, Inst. Plasma Phys. ; Twente U., Enschede) ; Jin, Huan (Hefei, Inst. Plasma Phys.) ; Fang, Zhen (CAS, HMFL, Hefei) ; Xiao, Guanyu (Hefei, Inst. Plasma Phys. ; Anhui U. Sci. Tech.) ; Ma, Hongjun (Hefei, Inst. Plasma Phys.) ; Liu, Fang (Hefei, Inst. Plasma Phys.) ; Liu, Huajun (Hefei, Inst. Plasma Phys.) ; Ma, Tao (Xian Jiaotong U.) ; Tan, Yunfei (Hua-Zhong U. Sci. Tech.) ; Chen, Wenge (CAS, HMFL, Hefei) et al.
The Institute of Plasma Physics at the Chinese Academy of Sciences is developing the REBCO cable in conduit conductor (CICC) technology for applications in next-generation nuclear fusion devices. The aim is to develop a CICC comprised of six REBCO sub-cables to satisfy the requirements of operation with a current of around 40 kA and a peak field of up to 20 T. [...]
2022 - 9 p. - Published in : Supercond. Sci. Technol. 35 (2022) 114003
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4.
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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5.
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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