View in EDS

Fast Ions in the Projected Globus-3 Tokamak. Part 1: Neutral Beam Injection.

Saved in:
Bibliographic Details
Title: Fast Ions in the Projected Globus-3 Tokamak. Part 1: Neutral Beam Injection.
Authors: Bakharev, N. N.1 (AUTHOR) bakharev@mail.ioffe.ru, Aleksandrov, A. S.1 (AUTHOR), Kiselev, E. O.1 (AUTHOR), Skrekel, O. M.1 (AUTHOR), Amirov, V. Kh.2 (AUTHOR), Balachenkov, I. M.1 (AUTHOR), Bondarchuk, E. N.3 (AUTHOR), Bondar, A. V.3 (AUTHOR), Brul, A. V.2 (AUTHOR), Varfolomeev, V. I.1 (AUTHOR), Voronova, A. A.3 (AUTHOR), Grosheva, A. D.3 (AUTHOR), Gusev, V. K.1 (AUTHOR), Davydenko, V. I.2 (AUTHOR), Deichuli, P. P.2 (AUTHOR), Donin, A. S.2 (AUTHOR), Zhiltsov, N. N.1 (AUTHOR), Kavin, A. A.3 (AUTHOR), Kapitonov, V. A.2 (AUTHOR), Kedrov, I. V.3 (AUTHOR)
Source: Plasma Physics Reports. Nov2025, Vol. 51 Issue 11, p1393-1408. 16p.
Subjects: Fast ions, Plasma heating, Magnetic fields, Neutral beams, Plasma confinement, Scientific experimentation, Particle range (Nuclear physics), Tokamaks
Abstract: This work presents the results of a study on the selection of neutral beam injection system parameters for the projected Globus-3 spherical tokamak. The focus is on optimizing the energy and injection geometry to minimize fast particle losses and achieve efficient plasma heating. Two operating scenarios are considered: with low (1.5 T, 0.8 MA) and high (1.8 T, 2 MA) toroidal magnetic field and plasma current parameters. It is shown that the optimal injection energy range is 50–60 keV, which ensures a balance between minimizing shine-through losses and efficient heating of the plasma core. The study also analyzes the effect of the toroidal magnetic field ripple on the fast ion confinement. It is established that the thermal loads on the tokamak wall due to fast particle losses do not exceed critical values, even with non-ideal positioning of the first wall elements. The simulation results demonstrate that a neutral beam injection system with a power of up to 11.5 MW is capable of providing ion heating up to 20–40 keV, generating a non-inductive current of up to 700 kA and high plasma rotation, which opens up opportunities for research in the hot ion mode. [ABSTRACT FROM AUTHOR]
Copyright of Plasma Physics Reports is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
Description
Abstract:This work presents the results of a study on the selection of neutral beam injection system parameters for the projected Globus-3 spherical tokamak. The focus is on optimizing the energy and injection geometry to minimize fast particle losses and achieve efficient plasma heating. Two operating scenarios are considered: with low (1.5 T, 0.8 MA) and high (1.8 T, 2 MA) toroidal magnetic field and plasma current parameters. It is shown that the optimal injection energy range is 50–60 keV, which ensures a balance between minimizing shine-through losses and efficient heating of the plasma core. The study also analyzes the effect of the toroidal magnetic field ripple on the fast ion confinement. It is established that the thermal loads on the tokamak wall due to fast particle losses do not exceed critical values, even with non-ideal positioning of the first wall elements. The simulation results demonstrate that a neutral beam injection system with a power of up to 11.5 MW is capable of providing ion heating up to 20–40 keV, generating a non-inductive current of up to 700 kA and high plasma rotation, which opens up opportunities for research in the hot ion mode. [ABSTRACT FROM AUTHOR]
ISSN:1063780X
DOI:10.1134/S1063780X25604110