The globus-m diagnostics design

Bulanin, V. V.; Chugunov, I.N.; Vildzunas, M. I.; Гаврилов, Г. А.; Gusev, V. K.; Минаев, В. Б.; Krikunov, S. V.; Mukhin, E. E.; Petrov, Yu. V.; Razdobarin, G. T.; Rozdestvenskiy, V. V.; Сахаров, Н. В.; Семенов, В. В.; Tolstyakov, S. Yu.; Aronov, A. M.; Kamach, Yu. E.; Shapiro, L. L.; Petrov, A. A.; Петров, В. Г.; Bender, S.E.; Agureev, B. A.; Trusillo, S. V.

doi:10.1080/10519990108224492

Cited by 4 publications

(2 citation statements)

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“…The beam is injected in the equatorial plane of the tokamak, tangentially to the magnetic axis, in the direction of the plasma current. The diagnostic system used in these experiments was described in [33]. Using data from magnetic diagnostics, the magnetic configuration and some integral parameters of the plasma column (such as the plasma stored energy and beta) are reconstructed with the use of the EFIT code [34,35].…”

Section: Experimental Studies Of Nbi Plasma Heatingmentioning

confidence: 99%

10.1007/s11452-008-2001-9

2010

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Results from experimental studies on the injection of high-energy neutral hydrogen beams into the plasma of the Globus-M spherical tokamak are reviewed. In the Introduction, the importance of these studies for implementing the controlled fusion research program and constructing the ITER tokamak is proved. Some problems related to the use of neutral beam injection in small and low-aspect-ratio tokamaks is analyzed. Results are presented from numerical simulations of the experiment by using the ASTRA transport code. It is shown that the use of neutral beam injection in the Globus-M tokamak ensures efficient ion heating and increases the plasma stored energy. The greater part of the review is devoted to the survey of experiments on the injection of 22-to 30-keV hydrogen and deuterium beams with a power of 0.4-0.8 MW into the plasma of the Globus-M spherical tokamak in a wide range of plasma currents and densities. The experimental results are analyzed and compared with the results of numerical simulations. The achievement of top plasma parameters is highlighted.

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Section: Experimental Studies Of Nbi Plasma Heatingmentioning

confidence: 99%

10.1007/s11452-008-2001-9

2010

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“…Diagnostics used during experiments on density increase and control include the whole complex of diagnostics equipment for the Globus-M tokamak [5].…”

Section: Diagnostics Improvementmentioning

confidence: 99%

Density limits and control in the Globus-M spherical tokamak

et al. 2006

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The results of the experimental campaign on Globus-M (R = 0.36 m, a = 24 m) devoted to investigating density limits and density control are reported. The experiments were performed at B tor = 0.4 T, I p = 0.18-0.25 MA, q 95 = 3.5-5 and plasma vertical elongation, κ ∼ 1.5-1.7. The density limits achieved with the gas puffing method of density control in the previous periods in ohmic heating (OH) regime are discussed. The progress made in OH scenario optimization helped the density to approach the Greenwald limit. Co-current neutral beam of deuterium with the power in the range of 0.45-0.6 MW at the beam energy of 28-29 keV was injected into deuterium target plasma at the early stage of the discharge, which allowed the density to overcome the Greenwald limit. Line averaged densities in excess of 1.5 × 10 20 m −3 were achieved, during the external gas puff. An ion temperature increase, measured by NPA was accompanied by a definite increase in the electron energy content, registered by Thomson scattering. Injection of a pure, highly ionized hydrogen plasma jet with a density up to 10 22 m −3 , total number of accelerated particles (1-5) × 10 19 and a flow velocity of ∼110 km s −1 was used as another instrument for density control. It increased plasma particle inventory in the Globus-M by ∼50% (from 0.65 × 10 19 to 1 × 10 19 ) in a single shot without target OH plasma parameter degradation. The injection resulted in a fast density increase with the time much shorter than with gas puff fuelling, which was confirmed by Thomson scattering measurements.

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