On-line plasma shape reconstruction algorithm in tokamaks and its verification in the Globus-M

Vasiliev, V. I.; Kostsov, Yu.A.; Lobanov, K.M.; Makarova, L.P.; Mineev, A. B.; Gusev, V. K.; Levin, Roy; Petrov, Yu. V.; Sakharov, N. V.

doi:10.1088/0029-5515/46/8/s08

Cited by 30 publications

(4 citation statements)

References 6 publications

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“…Quite positive experience of the RGTi graphite utilization in the Globus-M spherical tokamak helped to improve density control and to reach record densities. After the installation of the toroidal RGTi limiter inside the vessel the line averaged density up to 1.2 × 10 20 m −3 was reached [23]. This may be partly explained by the physical properties of the RGTi graphite-high density (2.2 g cm −3 ), high thermal conductivity and poor deuterium sorption ability.…”

Section: Discussionmentioning

confidence: 99%

In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

Гусев¹,

Alimov²,

Arkhipov³

et al. 2009

Nucl. Fusion

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The composition, morphology and structure of the mixed layers deposited onto the surface (deposits) after a preliminary carboboronization procedure (B/C : H layers deposition) and subsequent plasma–wall interaction in the different areas of the Globus-M spherical tokamak have been analysed. Globus-M is almost completely covered by recrystallized graphite protection tiles (currently about 90% of its inner vessel area facing to plasma). The deposit properties were examined by different diagnostic techniques (electron probe microanalysis, scanning electron microscope, x-ray diffraction, nuclear resonance reactions, thermal desorption spectroscopy, infrared Raman scattering and secondary ion mass spectroscopy) after sample exposure to plasma during 3000–10000 tokamak pulses. It was found that deposits existed even in high flux regions (separatrix strike points). The initial composition of the protective layers formed during boronization is dramatically modified during long-term plasma–wall interaction and resulted in significant intermixing of its components with materials of the vessel interior. The properties of the layers deposited onto the surfaces intensively interacting with plasma, as well as the composition of the layers deposited in the ‘shadowed’ zones are discussed. Deuterium retention in Globus-M was estimated relying upon the data on deuterium concentrations in the deposits that were measured by different methods. It is revealed that deuterium was absorbed only in the deposits and its concentration vanished in the bulk of the tiles. Conditions of deuterium desorption are analysed and the merits of recrystallized graphite are discussed.

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Section: Discussionmentioning

confidence: 99%

In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

Гусев¹,

Alimov²,

Arkhipov³

et al. 2009

Nucl. Fusion

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“…Electron (W e ) and ion (W i ) thermal energy content was determined by integrating electron and ion pressure profiles over the plasma volume. The equilibrium configuration of the plasma column was provided by the magnetic diagnostics [20] and equilibrium code PET [21]. Most of the plasma energy falls on the ion component-6 kJ, less on electrons-4 kJ.…”

Section: Lettermentioning

confidence: 99%

The first observation of the hot ion mode at the Globus-M2 spherical tokamak

et al. 2022

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Hot ion mode was recently achieved at the Globus-M2 spherical tokamak when toroidal magnetic field was as high as 0.9 T and plasma current 0.35 МА. The injection of two neutral beams with a total power of 0.7 MW and an energy of 30 keV into a plasma with major radius 0.36 m and minor radius 0.22 m (aspect ratio 1.6) made it possible to heat the plasma ions up to 4 keV, while electron density in the plasma center was as high as 8E+19 m^-3. The achievement of high temperatures became possible due to the good thermal insulation of the plasma.

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“…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]. The plasma density is monitored along three vertical chords by a microwave interferometer operating at a wavelength of 0.8 mm.…”

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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On-line plasma shape reconstruction algorithm in tokamaks and its verification in the Globus-M

Cited by 30 publications

References 6 publications

In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

In-vessel surface layer evolution during plasma–wall interaction in the Globus-M spherical tokamak

The first observation of the hot ion mode at the Globus-M2 spherical tokamak

10.1007/s11452-008-2001-9

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