Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system

Author

Heller, R. ; Darweschsad, S.M. ; Dittrich, G. ; Fietz, W.H. ; Fink, S. ; Herz, W. ; Hurd, F. ; Kienzler, A. ; Lingor, A. ; Meyer, I. ; Nöther, G. ; Süsser, M. ; Tanna, V.L. ; Vostner, Alexander ; Wesche, R. ; Wüchner, F. ; Zahn, G.

Author_Institution

Inst. for Tech. Phys., Forschungszentrum Karlsruhe, Germany

Volume

15

Issue

2

fYear

2005

fDate

6/1/2005 12:00:00 AM

Firstpage

1496

Lastpage

1499

Abstract

In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed.

Keywords

Tokamak devices; contact resistance; fusion reactor design; fusion reactor materials; high-temperature superconductors; superconducting magnets; thermal properties; 4.5 K; 50 K; 70 kA; CRPP Villigen; European Fusion Technology Programme; Forschungszentrum Karlsruhe; He mass flow rate; ITER TF coil; ITER magnet system; TOSKA facility; contact resistance; fusion magnet; heat load; high temperature superconductor current lead demonstrator; steady state condition; temperature profile; Copper; Helium; High temperature superconductors; Lead; Plasma temperature; Safety; Superconducting coils; Superconducting magnets; Temperature distribution; Testing; Current leads; 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.2005.849145

Filename

1439928