Globus-M spherical tokamak

Gusev, V. K.; Golant, V.E.; Gusakov, E. Z.; Dyachenko, V. V.; Irzak, M. A.; Минаев, В. Б.; Mukhin, E. E.; Novokhatskii, A. N.; Podushnikova, K.A.; Razdobarin, G. T.; Сахаров, Н. В.; Tregubova, E. N.; Uzlov, V.; Shcherbinin, O. N.; Belyakov, V. A.; Kavin, А.; Kostsov, Yu.A.; Kuzmin, E.; Soikin, V.F.; Kuznetsov, E. A.; Yagnov, V. A.

doi:10.1134/1.1259469

Cited by 73 publications

(32 citation statements)

References 3 publications

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“…А.Ф. Иоффе, представляет собой токамак нового поколения (большой радиус плазмы 0,36 м, малый -0,24 м, тороидальное магнитное поле 0,4 Тл), предназначенный для исследования физических процессов в плазме с диверторной конфигурацией плазменного шнура и отработки инженерных рекомендаций для сферических токамаков мегаамперного диапазона [10]. Эксперименты проводятся в широком диапазоне параметров дейтериевой плазмы (ток плазмы 100-250 кА, электронная концентрация (0,1-1,0)10 20 м Пробы собирались мягкой кисточкой в бумажные пакетики с заглушки фланца (3 на рис.…”

Section: экспериментальная техникаunclassified

Morphology and Composition of Dust and Debris Produced in Globus-M Tokamak

Залавутдинов¹,

Gorodetsky²,

Захаров³

et al. 2011

PAST-TF

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Section: экспериментальная техникаunclassified

Morphology and Composition of Dust and Debris Produced in Globus-M Tokamak

Залавутдинов¹,

Gorodetsky²,

Захаров³

et al. 2011

PAST-TF

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“…Fast atoms of the beam transport energy and momentum into plasma column and being trapped there as ions could heat and fuel the plasma and drive current. First NBI experiments performed on the T-11 tokamak [1] with parameters of injection and target plasma close to those in Globus-M [2] and TUMAN-3M [3] demonstrated efficient plasma heating. At the injection power of $0.6 MW for H 0 -beam injected into D þ -plasma the increase of hb T i up to 2% without a degradation of energy confinement was recorded.…”

Section: Introductionmentioning

confidence: 99%

Preparation of neutral beam injection experiments on Globus-M and TUMAN-3M tokamaks

Askinazi¹,

Barsukov

Golant

et al. 2003

Plasma Devices and Operations

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The neutral beam injection (NBI) experiments on the Globus-M and on the TUMAN3-M tokamaks in the Ioffe Institute are prepared. In order to maximize absorbed power and reduce ion orbit losses the transport modeling of the planed experiments was performed. On the base of the modeling the target plasma and neutral beam parameters as well as experiment geometry were chosen. It is shown that at plasma density 2 Â 10 19 m À3 and beam energy $25 keV the ''shine-through'' losses and the first-orbit losses are negligible. NBI power of 0.6-1.0 MW allow to increase ratio of the plasma pressure to the magnetic field pressure -b up to critical values ($20-30% for Globus-M).The paper describes results of numerical simulations and overview of status of NBI experiment preparations.

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“…Significant drawbacks of the START experiments were that the discharge duration was rather short and that the plasma parameters were too low to achieve a collisionless regime, typical of a fusion tokamak reactor. In the next-generation tokamaks (MAST [16], NSTX [17], and Globus-M [18]), which were put into operation in the late 1990s, the discharge duration far exceeds the energy and particle confinement times and the auxiliary heating power far exceeds the ohmic heating power. The main parameters of these tokamaks are listed in the table.…”

Section: Introductionmentioning

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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Globus-M spherical tokamak

Cited by 73 publications

References 3 publications

Morphology and Composition of Dust and Debris Produced in Globus-M Tokamak

Morphology and Composition of Dust and Debris Produced in Globus-M Tokamak

Preparation of neutral beam injection experiments on Globus-M and TUMAN-3M tokamaks

10.1007/s11452-008-2001-9

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