Abstract
The Steady State Tokamak (SST-1) employs superconducting PF coils with one pair of copper coils. A NbTi based 10 kA cable-in-conduit-conductor (CICC) having a cabling pattern of 3/spl times/3/spl times/3/spl times/5 has been chosen as the base conductor for the superconducting PF coils. The resistive pair of PF coils placed inside the vacuum vessel will have 20/spl times/22 mm/spl times/ mm, internally cooled Cu based conductor. The SST-1 PF magnets are designed for running both double null and single null nominal (220 kA) and high current (330 kA) plasmas. The current ramp up in the plasmas to 220 kA and 330 kA is done in 3 seconds using Lower Hybrid Current Drive (LHCD). A wide range of reference equilibria with elongation (/spl kappa/) in the range of 1.7-2.0, triangularity (/spl delta/) in the range of 0.4-0.7, 'li' in the range of 0.75-1.4 along with the control of the divertor strike points have been studied with the SST-1 PF coils. Presently, the engineering design and manufacturing details of the SST-1 PF coils are being carried out. The PF coil physical and operational characteristics, winding pack details, insulation and support details, interfaces and hydraulic schemes are discussed in this paper.
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