DocumentCode :
1098260
Title :
High Temperature Superconductor Current Leads for WENDELSTEIN 7-X and JT-60SA
Author :
Fietz, Walter H. ; Heller, Reinhard ; Kienzler, Andreas ; Lietzow, Ralph
Author_Institution :
Forschungszentrum Karlsruhe, Karlsruhe, Germany
Volume :
19
Issue :
3
fYear :
2009
fDate :
6/1/2009 12:00:00 AM
Firstpage :
2202
Lastpage :
2205
Abstract :
Forschungszentrum Karlsruhe has taken over the responsibility for the design, construction and testing of the High Temperature Superconductor (HTS) current leads for two fusion experiments, i.e. the stellarator WENDELSTEIN 7-X (W7-X) and the satellite tokamak JT-60SA. W7-X is presently under construction at the Greifswald branch of the Max-Planck-Institute for Plasma Physics and consists of 50 non-planar and 20 planar coils with a maximum conductor current of 17.6 kA. In total 14 current leads are required with a nominal current of 14 kA that are mounted upside down with the warm end at the bottom. In the frame of the Broader Approach Agreement between Japan and the EU and concomitantly to the ITER project, the satellite tokamak project JT-60SA has been agreed in 2006. The magnet system of JT-60SA consists of 18 toroidal field coils, 4 central solenoid modules and 7 poloidal field coils. In total 26 leads mounted in vertical, normal position are required. For W7-X and JT-60SA a common basic design will be used which will be adapted to the special needs of the machines. All current leads will be of the Cu-HTS binary type. The HTS part covers the range between 4.5 K and 60 K and is cooled by heat conduction from the 4.5 K end, only. The Cu heat exchanger is cooled with 50 K He and covers the range between 60 K and room temperature. The paper describes the status of the HTS current lead development for W7-X and JT-60SA.
Keywords :
Tokamak devices; bismuth compounds; calcium compounds; fusion reactor design; fusion reactor materials; gold alloys; heat conduction; heat exchangers; high-temperature superconductors; lead compounds; plasma toroidal confinement; silver alloys; stellarators; strontium compounds; superconducting coils; superconducting magnets; Bi-2223; Bi2-xPbxSr2Ca2Cu3O10-AgAu; HTS; HTS material; ITER project; JT-60SA design; Max-Planck-Institute; W7-X; WENDELSTEIN 7-X; central solenoid modules; current 14 kA; fusion experiments; heat conduction; heat exchanger; high temperature superconductor current; magnet system; poloidal field coils; satellite tokamak; stellarator; temperature 4.5 K to 60 K; temperature 60 K to 298 K; toroidal field coils; Current leads; JT-60SA; Wendelstein 7-X; fusion magnets; high temperature superconductor;
fLanguage :
English
Journal_Title :
Applied Superconductivity, IEEE Transactions on
Publisher :
ieee
ISSN :
1051-8223
Type :
jour
DOI :
10.1109/TASC.2009.2019550
Filename :
5109607
Link To Document :
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