Neutral Injection Complex for Globus-M2 Spherical Tokamak

Shchegolev, P. B.; Minaev, V. B.; Telnova, A. Yu.; Varfolomeev, V. I.; Gusev, V. K.; Esipov, L. A.; Zhiltsov, N. S.; Kolmogorov, V. V.; Kondakov, A. A.; Kurskiev, G. S.; Miroshnikov, I. V.; Panasenkov, A. A.; Sorokin, A. V.; Shikhovtsev, I. A.

doi:10.1134/s1063780x23601098

Plasma Phys. Rep.

2023

DOI: 10.1134/s1063780x23601098

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Neutral Injection Complex for Globus-M2 Spherical Tokamak

P. B. Shchegolev,

V. B. Minaev,

A. Yu. Telnova

et al.

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2024

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Cited by 5 publications

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Overview of neutral beam injectors for plasma heating and diagnostics developed at Budker INP

Shikhovtsev,

Ivanov,

Davydenko

et al. 2024

J. Plasma Phys.

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An overview of the neutral beam injectors developed at the Budker Institute of Nuclear Physics in Novosibirsk during the last 10 years is presented. These neutral injectors are used for plasma diagnostics, heating and current drive in modern fusion devices with magnetic confinement. An arc or a radio-frequency (RF) discharge generates a plasma in the ion sources of the injectors, and a positive hydrogen or deuterium ion beam is extracted and accelerated by a multiaperture ion-optical system (IOS). The accelerated ion beam is converted into a neutral one in a gas target. The precision multiaperture IOS with spherically concave electrodes provides ballistic focusing of the neutral beam. The high-energy, high-power beam injector based on negative ions, which is currently under development, is described as well. It comprises a RF negative ion source and a wide-aperture electrostatic accelerator separated from the source by a low-energy beam transport line, thereby improving the injector reliability.

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Overview of neutral beam injectors for plasma heating and diagnostics developed at Budker INP

Shikhovtsev,

Ivanov,

Davydenko

et al. 2024

J. Plasma Phys.

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Confinement, heating, and current drive study in Globus-M2 toward a future step of spherical tokamak program in Ioffe Institute

Kurskiev,

Minaev,

Sakharov

et al. 2024

Physics of Plasmas

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This paper highlights the most important results achieved at the spherical tokamak Globus-M2 with a high magnetic field. This paper also covers the most important topics of fusion research: thermal energy confinement in regimes with neutral beam injection, toroidal Alfvén eigenmode and correspondent fast ions confinement issues, L-H transition, turbulence suppression and edge-localized modes' behavior, experimental and theoretical study of regimes with nitrogen seeding that allow to significantly reduce thermal loads on the divertor plates, and experiments and simulations of lower hybrid current drive. The research results provide the basis for the next step toward a fusion neutron source—the development of the Globus-3 spherical tokamak.

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First results of turbulence investigation on Globus-M2 using radial correlation Doppler reflectometry

PONOMARENKO,

YASHIN,

GUSEV

et al. 2024

Plasma Sci. Technol.

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The first results of investigation of the turbulence structure using Doppler backscattering (DBS) on the Globus-M2 tokamak are presented. A one-channel DBS system with a variable probing frequency within the 18-26 GHz range was installed to investigate the edge plasma at normalized minor radii ρ = 0.9 – 1.1. Radial correlation Doppler reflectometry was used to study the changes in turbulence eddies after the LH transition. Correlation analysis was applied to the phase derivative of complex IQ signals of the DBS diagnostic as it contains information about the poloidal plasma rotation velocity. In L-mode the radial correlation length Lr is estimated to be 3 cm and after transition to H-mode reduces to approximately 2 cm. Gyrokinetic modelling in a linear local approximation using code GENE indicates that the instability with positive growth rates at the normalized minor radius ρ = 0.75 in L-mode and H-mode on Globus-M2 was the ion temperature gradient (ITG) mode.

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Neutral Injection Complex for Globus-M2 Spherical Tokamak

Cited by 5 publications

References 18 publications

Overview of neutral beam injectors for plasma heating and diagnostics developed at Budker INP

Overview of neutral beam injectors for plasma heating and diagnostics developed at Budker INP

Confinement, heating, and current drive study in Globus-M2 toward a future step of spherical tokamak program in Ioffe Institute

First results of turbulence investigation on Globus-M2 using radial correlation Doppler reflectometry

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