The conceptual design of SST-1 tokamak has been finlised at the institute of plasma research. The SST-1 tokamak is being designed as a steady state tokamak with superconducting toroidal and poloidal field magnets, RF and neutral current drives and RF current heating. While the plasma equilibrium and shaping is provided by the superconducting poloidal field coils, plasma start-up and current ramp-up upto certain extent is desirable by a resistive ohmic transformer, as the stability of superconducting cable demands a limited rate of change of current in these coils so as to avoid the quenching in these coils and thus rules out the possibility of using these coils for the plasma start-up. The ohmic transformer consists of a central solenoid and two sets of compensating coils, which are required to minimise the stray fields of central solenoid in the plasma volume. The ohmic transformer has been designed to store a flux of 1.4 Vs, with inner radius 20 cm, outer radius 32 cm and height 260 cm. The central magnetic field required to produce this flux is 6.4 T. This field is provided by the 672 turns, which are arranged in the form of 6 layers with 112 turns each. Each turn has cross-sectional area of 19 mm X 22.7 mm, with a central extrusion of 8 mm, for the coolant flow. The compensation of error fields has been done by two sets of coils, which provide a stable quadrupole type minima. The error fields are of the order of 18 gauss at the plasma edge . The position of the coils and the corresponding ampere-turns are computed using an optimization program. The 78.5 MJ of the energy deposited in the coils during the 7.5 sec current pulse will be removed by flowing water through the 9 cooling channels of 8 mm diameter. The forces and stresses on the coils have been estimated using EFFI code. The design of central solenoid and the compensating coils along with the thermal requirements will be discussed . Calculations for the Lorentz force and internal stresses resulting from them will also be presented.