Abstract
In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have been developing a 60 W current lead for the ITER TF coils using high temperature superconductors. In part 3 of the task, a 20 kA HTS current lead was assembled using two Bi-2223 modules manufactured in industry. The performance test was carried out at NIFS, Japan, as part of the LIME project. The test covers the electrical and thermal behaviour in both steady state and transient operation. Current sharing was observed between two modules and the quench current of the current lead was evaluated about 30 kA at the design conditions. The results suggest that it is possible to satisfy all requirements needed for the leads of the ITER TF coils.
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