Test results on systems developed for SST-1 tokamak

A steady state superconducting tokamak SST-1 is being fabricated at the Institute for Plasma Research (IPR). SST-1 is a large aspect ratio tokamak, configured to run double null diverted plasmas with significant elongation of 1.7 to 1.9 and triangularity of 0.4 to 0.7. The machine has a major radius of 1.1 m, minor radius of 0.20 m, a toroidal field of 3.0 T at plasma center and a plasma current of 220 kA and plasma discharge duration will be 1000 s. Full scale prototypes of superconducting coil has been developed and tested successfully. Test and commissioning result for the Liquid Helium plant will be presented. High power CW tests of the indigenously designed and fabricated rf components along with other high power components would be reported here. A Neutral Beam Injection (NBI) with peak power of 0.8 MW with variable beam energy in range of 10-80 keV will be used as additional auxiliary heating system. A proto-type cryocondensation pump having overall dimensions of 3.2mx0.6mx0.3m has been fabricated and tested for pumping speed of 105 l/s in deuterium at 4.5 K. Test results on all proto types and on already fabricated components/systems will be presented in this paper. (author)