SST-1 is a steady state tokamak which is designed to operate with superconducting magnetic field coils to produce highly shaped double null diverted plasma. The major plasma radius is 1.1 m, minor radius is 0.20 m and elongation is 1.6 to 2.0. The machine is designed for plasma discharge duration of 1000 s with non-inductive current drive. The design of the vacuum vessel and cryostat is presented. The design analysis using analytical methods and finite element methods has been carried out to evaluate the stress developed on the vessel and cryostat.
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