In the frame of tile European Fusion Technology Programme, the Forschungsze
ntrum Karlsruhe and the CRPP Villigen have been developing a 60 W current l
ead for the ITER TF coils using High Temperature Superconductor (HTS), In p
art 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 sh
aring was observed between two modules and the quench current of the curren
t lead was evaluated about 30 kA at the design conditions. The results sugg
est that it is possible to satisfy all requirements needed for the leads of
the ITER TF coils.