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A visible fast camera coupled with an image intensifier was employed to view turbulent coherent plasma structures (blobs) at the gas plume being puffed through a poloidal limiter. The image intensifier amplifies the light intensity thereby allowing the imaging system to be operated at ultra-short exposure times down to 100 ns. The idea behind operating at such low exposure times is to study the features of the turbulent coherent structure at smaller time scales than usual. Possible effects that can distort the blob's characteristics if the camera exposure time is larger than its dynamics are the smoothing effect (averaging of multiple events within the integration time) or the blurring effect (integrating the emission in time during the movement of the blob). This can be especially important when looking for space scales below 1 cm, which we call the fine structure. The image intensifier, however, introduces some grainy noise to the camera image and in the fine structure analysis this noise can sometimes become comparable to the size of the structure itself and may lead to a false interpretation of the image. To distinguish real physical signal from noise we get two simultaneous images with the same view and compare them. We call this the double imaging technique and it allows us to validate the detected blob shape to scales down to a few millimetres, limited by our optical resolution. We have studied the influence of camera exposure time on the blob features and observed that for shorter times more intense bursts are recorded in the TJ-II stellarator. The most intense bursts are smoothed, even using an exposure time of 1 µs. Further, for the low-density electron cyclotron resonance heated (ECRH) plasmas analysed, the detected structures with positive density above the background (blobs) show strong intensity excursions not visible in the negative structures (holes), these however being more numerous at the low-intermediate intensity range. Other results concerning blob characteristics are shown.

A steady state superconducting tokamak (SST-1) has been commissioned after the successful experimental and engineering validations of its critical sub-systems. During the 'engineering validation phase' of SST-1; the cryostat was demonstrated to be leak-tight in all operational scenarios, 80 K thermal shields were demonstrated to be uniformly cooled without regions of 'thermal runaway and hot spots', the superconducting toroidal field magnets were demonstrated to be cooled to their nominal operational conditions and charged up to 1.5 T of the field at the major radius. The engineering validations further demonstrated the assembled SST-1 machine shell to be a graded, stress-strain optimized and distributed thermo-mechanical device, apart from the integrated vacuum vessel being validated to be UHV compatible etc. Subsequently, 'field error components' in SST-1 were measured to be acceptable towards plasma discharges. A successful breakdown in SST-1 was obtained in SST-1 in June 2013 assisted with electron cyclotron pre-ionization in the second harmonic mode, thus marking the 'first plasma' in SST-1 and the arrival of SST-1 into the league of contemporary steady state devices.Subsequent to the first plasma, successful repeatable plasma start-ups with E ∼ 0.4 V m −1 , and plasma current in excess of 70 kA for 400 ms assisted with electron cyclotron heating pre-ionization at a field of 1.5 T have so far been achieved in SST-1. Lengthening the plasma pulse duration with lower hybrid current drive, confinement and transport in SST-1 plasmas and magnetohydrodynamic activities typical to large aspect ratio SST-1 discharges are presently being investigated in SST-1. In parallel, SST-1 has uniquely demonstrated reliable cryo-stable high field operation of superconducting TF magnets in the two-phase cooling mode, operation of vapour-cooled current leads with cold gas instead of liquid helium and an order less dc joint resistance in superconducting magnet winding packs with high transport currents. In parallel, SST-1 is also continually getting up-graded with first wall integration, superconducting central solenoid installation and over-loaded MgB 2 -brass based current leads etc. Phase-1 of SST-1 up-gradation is scheduled by the first half of 2015, after which long pulse plasma experiments in both circular and elongated configurations have been planned in SST-1.

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Steady State Tokamak (SST-1) vacuum vessel baking as well as baking of the first wall components of SST-1 are essential to plasma physics experiments. Under a refurbishment spectrum of SST-1, the nitrogen gas heating and supply system has been fully refurbished. The SST-1 vacuum vessel consists of ultra-high vacuum (UHV) compatible eight modules and eight sectors. Rectangular baking channels are embedded on each of them. Similarly, the SST-1 plasma facing components (PFC) are comprised of modular graphite diverters and movable graphite based limiters. The nitrogen gas heating and supply system would bake the plasma facing components at 350 o C and the SST-1 vacuum vessel at 150 o C over an extended duration so as to remove water vapour and other absorbed gases. An efficient PLC based baking facility has been developed and implemented for monitoring and control purposes. This paper presents functional and operational aspects of a SST-1 nitrogen gas heating and supply system. Some of the experimental results obtained during the baking of SST-1 vacuum modules and sectors are also presented here.