Thermo hydraulic and quench propagation characteristics of SST-1 TF coil

Sharma, A.N.; Pradhan, Subrata; Duchateau, J.L.; Khristi, Y.; Prasad, Upendra; Doshi, K.; Varmora, P.; Patel, Dipak; Tanna, V. L.

doi:10.1016/j.fusengdes.2013.12.058

Cited by 4 publications

(2 citation statements)

References 12 publications

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“…Total weight of SCMS is around 40 Tons which is to be cooled by force flow supercritical helium at 4.5 K, 4 bar. Prior to assembly on SST-1 machine shell, each TF coils have been tested for its electromagnetic, thermo hydraulic and mechanical performances at rated operating currents of 10 kA [3]. SST-1 magnets system has flexibility to operate in single phase (supercritical) as well as two-phase with and without sub-cooling using HRL system.…”

Section: Introductionmentioning

confidence: 99%

Cryogenic heat loads analysis from SST-1 plasma experiments

Bairagi

Tanna

Pradhan

2017

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract.Cryogenic heat load analysis is an important aspect for stable operation of Tokamaks employing large scale superconducting magnets. Steady State Superconducting Tokamak (SST-1) at IPR is equipped with superconducting magnets system (SCMS) comprising sixteen numbers of modified 'D' shaped toroidal field (TF) and nine poloidal field (PF) superconducting coils which are wound using NbTi/Cu based cable-in conduit conductor (CICC). SST-1 magnets operation has flexibility to cool either in two-phase with sub-cooling, two-phase without sub-cooling or single phase (supercritical) helium using a dedicated 1.3 kW helium refrigerator cum liquefier (HRL). Here, we report gross heat losses for integrated TF superconducting magnets of SST-1 during the plasma campaign using cryogenic helium supply/return thermodynamic data from cryoplant. Heat loads mainly comprising of steady state as well as transient loads are smoothly absorbed by SST-1 cryogenic helium plant during plasma experiments. The corresponding heat produced in the coils is totally released to the helium flowing through the TF coils, which in turn is dumped into liquid helium stored in main control Dewar. These results are very useful reference for heat loss analysis for TF as well as PF coils and provides database for future operation of SST-1 machine.

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Section: Introductionmentioning

confidence: 99%

Cryogenic heat loads analysis from SST-1 plasma experiments

Bairagi

Tanna

Pradhan

2017

IOP Conf. Ser.: Mater. Sci. Eng.

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“…The initial commissioning in 2006 was not successful [2]. Prior to the re-assembly of SST-1, several of its sub-systems have been meticulously tested redundantly at multiple stages [3][4][5][6][7][8][9]. Subsequently, in post-machine shell assembly, SST-1 has undergone a rigorous 'engineering validation' of the assembled sub-systems, which are described in section 2 of this paper.…”

Section: Introductionmentioning

confidence: 99%

The first experiments in SST-1

Pradhan¹,

Khan²,

Tanna³

et al. 2015

Nucl. Fusion

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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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