I. Introduction
Acable-In-Conduit-Conductor (CICC), as used for large scale superconducting coils, is made of many superconducting strands which are twisted in multiple steps. The CICC has superior characteristics, such as large current capacity, high stiffness, and low AC loss. Therefore, the CICC is suitable for magnetic confinement fusion reactors and the main superconducting magnets of International Thermonuclear Experimental Reactor (ITER) are formed from CICC. Since the superconducting magnets in ITER consist of several coils, the coils are jointed electrically at the ends of CICCs. In a CICC Joint for ITER Toroidal Field (TF) coils, two cables without conduit (jacket) are inserted into a copper sleeve to join the two cables. This method is called a “Wrap Joint” and the current flows from one cable to the other through the copper sleeve [1]. Fig. 1 shows the schematic view of the CICC Wrap Joint.
Schematic view of the CICC wrap joint.