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Manufacture and Test of ITER 10-kA HTSCL Prototypes
/ Zhou, Tingzhi (Hefei, Inst. Plasma Phys.) ; Ding, Kaizhong (Hefei, Inst. Plasma Phys.) ; Liu, Chenglian (Hefei, Inst. Plasma Phys.) ; Lu, Kun (Hefei, Inst. Plasma Phys.) ; Ran, Qingxiang (Hefei, Inst. Plasma Phys.) ; Song, Yuntao (Hefei, Inst. Plasma Phys.) ; Niu, Erwu (Tsinghua U., Beijing, KLPRI) ; Bauer, Pierre (Cadarche, CEN) ; Devred, Arnaud (Cadarche, CEN) ; Lee, Seungje (Cadarche, CEN) et al.
To carry current for the ITER correction coils, the 10-kA high-temperature superconducting current leads studied here are designed. Current leads provide the transition from 4.5-K low temperature to room temperature. [...]
2016 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 26 (2016) 4802505
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2.
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Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
/ Ding, Kaizhong (Hefei, Inst. Plasma Phys.) ; Zhou, Tingzhi (Hefei, Inst. Plasma Phys.) ; Ballarino, Amalia (CERN) ; Gung, Chenyu (Southampton U.) ; Lu, Kun (Hefei, Inst. Plasma Phys.) ; Song, Yuntao (Hefei, Inst. Plasma Phys.) ; Niu, Erwu (Beihang U.) ; Bauer, Pierre (BIAM, St Paul lez Durance) ; Devred, Arnaud (BIAM, St Paul lez Durance) ; Lee, Seungje (BIAM, St Paul lez Durance) et al.
High temperature superconducting current leads (HTS-CL) are designed to supply the current to the large superconducting ITER magnets for the operation with reduced heat load to the cryogenic system. The Toroidal field (TF) current leads are the largest with a current capacity of 68 kA each. [...]
2019 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 29 (2019) 4802605
fulltext from publisher: HTML;
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3.
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Progress of the ITER Correction Coils in China
/ Wei, J (Hefei, Inst. Plasma Phys.) ; Wu, W (Hefei, Inst. Plasma Phys.) ; Han, S (Hefei, Inst. Plasma Phys.) ; Yu, X (Hefei, Inst. Plasma Phys.) ; Du, S (Hefei, Inst. Plasma Phys.) ; Li, C (Hefei, Inst. Plasma Phys.) ; Fang, C (Hefei, Inst. Plasma Phys.) ; Wang, L (Hefei, Inst. Plasma Phys.) ; Zheng, W (Hefei, Inst. Plasma Phys.) ; Liu, L (Hefei, Inst. Plasma Phys.) et al.
The ITER Correction Coils (CC) include three sets of six coils each, distributed symmetrically around the tokamak to correct error fields. Each pair of coils, located on opposite sides of the tokamak, is series connected with polarity to produce asymmetric fields. [...]
2014 - 5.
- Published in : IEEE Trans. Appl. Supercond. 24 (2014) 4202005
In : 23rd International Conference on Magnet Technology, Boston, MA, USA, 14 - 19 Jul 2013, pp.4202005
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4.
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Development of HTS Current Leads for the ITER Project
/ Bauer, P. (BIAM, St Paul lez Durance) ; Ballarino, A (CERN) ; Devred, A (CERN) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Dong, Y (Hefei, Inst. Plasma Phys.) ; Niu, E (Unlisted, CN) ; Du, Q (Hefei, Inst. Plasma Phys.) ; Gung, C Y (BIAM, St Paul lez Durance) ; Han, Q (Hefei, Inst. Plasma Phys.) ; Heller, R (KIT, Karlsruhe) et al.
The HTS current leads for the ITER project will be the largest ever operated, with unprecedented currents, up to 68 kA and voltages, up to 14 kV. According to the ITER agreement they will be provided in-kind by China. [...]
2020 - 8 p.
- Published in : IOP Conf. Ser. Mater. Sci. Eng. 756 (2020) 012032
fulltext from publisher: PDF;
In : Conference on Cryogenic Engineering and on International Cryogenic Materials, Hartford, Connecticut, 21 - 25 Jul 2019, pp.012032
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5.
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Design of the HTS Current Leads for ITER
/ Ballarino, A (CERN) ; Bauer, P (Euratom, St. Paul Lez Durance) ; Bi, Y (Hefei, Inst. Plasma Phys.) ; Devred, A (Euratom, St. Paul Lez Durance) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Foussat, A (Euratom, St. Paul Lez Durance) ; Mitchell, N (Euratom, St. Paul Lez Durance) ; Shen, G (Hefei, Inst. Plasma Phys.) ; Song, Y (Hefei, Inst. Plasma Phys.) ; Taylor, T (CERN) et al.
Following the design, fabrication and test of a series of trial leads, designs of the three types of current leads required for ITER have been developed, and targeted trials of specific features are in progress on the way to fabrication and testing of prototype units. These leads are of the hybrid type with a cold section based on the use of high temperature superconductor (HTS) and a resistive section cooled by forced flow of helium gas, optimized for operation at 68 kA, 55 kA and 10 kA. [...]
CERN-ATS-2012-047.-
Geneva : CERN, 2012 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 22 (2012) 4800304
Fulltext: PDF;
In : 22nd International Conference on Magnet Technology, Marseille, France, 12 - 16 Sep 2011
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6.
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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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7.
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Qualification of Fin-Type Heat Exchangers for the ITER Current Leads
/ Ballarino, A (CERN) ; Bauer, P (Euratom, St. Paul Lez Durance) ; Bordini, B (CERN) ; Devred, A (Euratom, St. Paul Lez Durance) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Niu, E ; Sitko, M (CERN) ; Taylor, T ; Yang, Y (Southampton U.) ; Zhou, T (Hefei, Inst. Plasma Phys.)
The ITER current leads will transfer large currents of up to 68 kA into the biggest superconducting magnets ever built. Following the development of prototypes and targeted trials of specific manufacturing processes through mock-ups, the ASIPP (Chinese Institute of Plasma Physics) is preparing for the series fabrication. [...]
2015
- Published in : IOP Conf. Ser. Mater. Sci. Eng. 101 (2015) 012119
IOP Open Access article: PDF;
In : Advances in Cryogenic Engineering: Cryogenic Engineering Conference, Tucson, AZ, USA, 28 Jun - 2 Jul 2015, pp.012119
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8.
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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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9.
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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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10.
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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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