DocumentCode :
2758978
Title :
High Temperature Superconductor Current Leads Proposal for ITER
Author :
Fietz, W.H. ; Heller, R. ; Lietzow, R. ; Tanna, V.L. ; Zahn, G. ; Wesche, R. ; Salpietro, E. ; Vostner, A.
Author_Institution :
Inst. fur Tech. Phys., Kernforschungszentrum Karlsruhe
fYear :
2005
fDate :
Sept. 2005
Firstpage :
1
Lastpage :
5
Abstract :
In the ITER superconducting magnet system, operation currents up to 68 kA are required that have to be transferred from room temperature (RT) to 4.5 K by specially designed current leads (CL). The ohmic losses and the thermal conduction of conventional CL cause high heat loads to the refrigeration system. This load can be reduced drastically by the use of high temperature superconductor (HTS) current leads because the superconducting HTS part of this CL causes no ohmic losses and very poor thermal conduction. The Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead using Bi-2223 HTS superconductor in the frame of the European Fusion Technology Programme. This HTS CL was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe showing that the current of 68 kA can be carried by the CL even when the highest temperature in the HTS part is 85 K. The CL shows a large safety margin in case of a loss of coolant and even cooling with LN2 has been demonstrated. The option that all ohmic losses in the temperature range between 4.5 K and approx. 80 K can be eliminated using HTS CL is very attractive for ITER because savings in investment and operation costs are possible by removing this load from the cryogenic system. The consequences with respect to investment and operation costs are discussed comparing the ITER design with and without HTS CL which demonstrates that HTS current leads are very attractive and should be used for ITER
Keywords :
bismuth compounds; calcium compounds; cryogenics; fusion reactor design; fusion reactor materials; fusion reactor operation; fusion reactor safety; high-temperature superconductors; refrigeration; strontium compounds; superconducting magnets; thermal conductivity; 298 to 4.5 K; 68 kA; 70 kA; Bi2Sr2Ca2Cu3O; CL; CRPP Villigen; European Fusion Technology Programme; Forschungszentrum Karlsruhe; ITER superconducting magnet system; LN2; TOSKA facility; coolant loss; cooling; cryogenic system; heat loads; high temperature superconductor current leads; ohmic losses; operation costs; operation currents; refrigeration system; room temperature; safety margin; thermal conduction; Costs; High temperature superconductors; Investments; Proposals; Refrigeration; Safety; Superconducting magnets; Testing; Thermal conductivity; Thermal loading; Current Lead; HTS; HTS Current lead; ITER;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
Type :
conf
DOI :
10.1109/FUSION.2005.252873
Filename :
4018907
Link To Document :
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