Abstract
A novel concept of bridge joint for Poloidal field (PF) magnet of SST-1 with damaged winding pack has been realized. This joint has been fabricated on 5th and 6th layers of PF#3T coil winding pack (WP) after validation at 10kA at liquid helium temperature of 4.2K in current lead test chamber. The joint resistance of bridge joint was measured ∼1.6nΩ at flat top DC current of 10kA. This type of joint could be economically useful for revival of a shorted and damaged WP superconducting PF magnets of Tokamaks. In this paper, details of bridge joint design, fabrication and validations are discussed.
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