Results of the model coil tests for the cable-in-conduit conductor for SST-1 tokamak

Anashkin, O.P.; Ivanov, D.P.; Кейлин, В.Е.; Kopeikin, Nikolai; Ковалев, И. А.; Krivykh, A. V.; Kruglov, S. L.; Лысенко, В. В.; Novikov, S. I.; Patrikeev, V. M.; Pradhan, Subrata; Saxena, Y. C.; Scherbakov, V. I.; Shugaev, I.; Stepanov, V.

doi:10.1109/tasc.2002.1018467

Cited by 10 publications

(2 citation statements)

References 5 publications

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“…MC was charged up to 12 000 A corresponding to 6.2 T of maximum self-field, with a mass flow rate of 0.5 g/s. Several other tests in ac magnetic fields that were done on MC to replicate all possible scenarios during the SST-1 plasma operation are described in [17].…”

Section: Coil Test Resultsmentioning

confidence: 99%

Cryogenic Acceptance Tests of SST-1 Superconducting Coils

Sharma

Prasad

Doshi

et al. 2015

IEEE Trans. Appl. Supercond.

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Toroidal field (TF) and poloidal field (PF) coils of steady-state superconducting tokamak (SST-1) have been fully refurbished to ensure cryostable and low-dc-resistance interpancake and intercoil joints, helium leak tightness of the winding pack, and > 10 MΩ winding pack to ground insulation resistance under cold conditions. As per SST-1 mission mandate, all TF coils and PF3 Top had been cold tested at full operational parameters. A dedicated large coil test facility was integrated for these tests. Specially adapted solutions such as magnet preparation cum transport stand, demountable busbar supports, demountable sensor mountings, reusable joints for busbar connections inside cryostat, etc., were developed. These measures led to timely and successful completion of cold tests and integration of the magnet system on to the SST-1 machine shell. The functionality of various diagnostics of the magnet system was also established during these tests. Details of coil refurbishment, test facility, test campaigns, and some important test results are reported in this paper. in solid-nitrogen-cooled MgB 2 -based persistent magnet development. Since 2006, he has been working with the SST-1 Magnet Group, Institute for Plasma Research, Gandhinagar, India. His current research interests include development of superconducting joint for MgB 2 conductors; design, analysis, development, and validation of superconducting magnets. A. Panchal received the B.E. degree in mechanical engineering. He is currently working with the SST-1 Magnet Group. His research interests include tool development and fabrication of superconducting magnets.S. J. Jadeja is currently a Welder with the SST-1

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Section: Coil Test Resultsmentioning

confidence: 99%

Cryogenic Acceptance Tests of SST-1 Superconducting Coils

Sharma

Prasad

Doshi

et al. 2015

IEEE Trans. Appl. Supercond.

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“…Moreover, the temperature reserve can decrease down to 0.8-0.7 K after 500 s plasma operation due to conductor heating by fast neutrons. The stability margin for the conductors of T-7 [1], T-15 [2] and SST-1 [3] were investigated in pulse magnetic field (PMF) to be convinced of its operability. In the case of fast plasma current disruption the electromagnetic time constant is 16 ms [4] and in the region of maximum background field (12 T) at 15 MA plasma current.…”

Section: Introductionmentioning

confidence: 99%

Eddy Current Loss in Superconducting Cable-in-Conduit Conductor (CICC)

Lelekhov¹,

Кейлин

Ковалев

et al. 2012

IEEE Trans. Appl. Supercond.

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The Conductor of the toroidal field (TF) coils in Tokamaks are exposed to high amplitude pulse magnetic field (PMF) parallel to conductor axis during plasma disruption. A new experimental method for losses investigation in superconducting cable-in-conduit conductor (CICC) was used in this work. The method is based on a high sensibility of gas pressure in a closed volume to the energy input and allows measuring hysteresis losses with sufficient precision (when the decay rate of PMF is small) and the sum of hysteresis and eddy current losses (when the decay rate of PMF is high). Eddy current losses are rather higher than the coupling ones in CICC when PMF is parallel to the conductor axis. Therefore short samples (length is smaller than the last twist pitch) can be used for such investigations. The test facility for investigating the losses was developed and manufacturing at the "Kurchatov Institute". The sample of the ITER TF conductor was exposed to PMF with different amplitude and electromagnetic time constant. As result of the experimental investigation the electromagnetic time constant and the resistivity of the bundle were determined. The maximum temperature of the strands during PMF exposure was calculated numerically.

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