Superconducting CICC for SST-1 tokamak magnets

The SST-1 tokamak is being designed for steady state operation with plasma durations in the range of 100-1000 s. Both the toroidal field coils (TFC) and the poloidal field coils (PFC) in the SST-1 tokamak are superconducting. TF coils are required to produce a magnetic field of 3 T at 1.05 m from machine axis. The maximum field seen by the TF coil conductor will be /spl les/4.3 T. The cable for the TF coils has, therefore, been designed for a field of 5 T at the conductor. The PFC are used for plasma shaping and equilibrium and the magnetic field on the PFC conductor is estimated to be /spl les/3.2 T. Hence a cable designed for 5 T operation will be suitable for PFC also. Subjected to the stability against the disturbances generated by the current ramping in the PFC. We have designed two Cable-in-conduit-conductor (CICC) type cables, one with copper conduit (to be preferably used with the TFC) and other with Stainless Steel conduit to be used with PFC. In the following we describe some design aspects' of these cables and discuss the stability of these cables against disturbances.