Conceptual design of ELM control coils for the TCABR tokamak

An upgrade of the Tokamak à Chauffage Alfvén Brésilien (TCABR) is being designed to make it capable of creating a well controlled environment where the impact of resonant magnetic perturbation (RMP) fields on edge localised modes can be addressed over a wide range of ( i ) plasma shapes, ( ii ) divertor configurations, ( iii ) RMP coil geometries and ( iv ) perturbed magnetic field spectra. To this end, a unique set of in-vessel RMP coils is being designed and, in this work, their conceptual design is presented. This unique set of coils is composed of three toroidal arrays of coils on the low field side and three toroidal arrays of coils on the high field side. Each of these six toroidal arrays is composed of 18 coils thus allowing for the creation of RMP fields with toroidal mode numbers n ≤ 9 and with increased control of the poloidal mode number spectrum. To study dynamical effects of RMP fields of different toroidal mode numbers, all rotating simultaneously with different velocities, each of the 108 RMP coils will be powered independently by power supplies that can provide voltages of up to 4 kV and electric currents of up to 2 kA, with frequencies varying continuously from 0 Hz up to 10 kHz. A set of physical criteria were used to determine the optimal coil geometry and their respective number of turns to reduce the coil currents and voltages during operation with alternate current. The conceptual design was carried out using both the vacuum approach (no plasma response) and the single-fluid response approach, which accounts for the response of a linear, single-fluid, visco-resistive plasma calculated using the M3D-C 1 code. • Design of RMP coils. • Plasma response to externally applied magnetic perturbations. • ELM control by RMP fields with n t o r ≤ 9 . • Application of RMP fields from both LFS and HFS.

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Publication Details

Journal
Fusion Engineering and Design
Published
2025-01-09
DOI
https://doi.org/10.1016/j.fusengdes.2024.114788
Citations
1
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.87

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article

Conceptual design of ELM control coils for the TCABR tokamak

D.M. Orlov, N.M. Ferraro, Roberto Ramos, Y. P. Asnis et al.
1 citations
Fusion Engineering and Design
Magnetic confinement fusion research
1.87
article

Conceptual design of ELM control coils for the TCABR tokamak

D.M. Orlov, N.M. Ferraro, Roberto Ramos, Y. P. Asnis, Gustavo Paganini Canal, Jorge Fernandes, J. H. F. Severo, Fuad Kassab, A. Kleiner, N. M. Kot, E. Seegyoung Seol, R. M. O. Galvão, André S. Bouzan, Felipe Machado Salvador
article en
1 citations

Abstract

An upgrade of the Tokamak à Chauffage Alfvén Brésilien (TCABR) is being designed to make it capable of creating a well controlled environment where the impact of resonant magnetic perturbation (RMP) fields on edge localised modes can be addressed over a wide range of ( i ) plasma shapes, ( ii ) divertor configurations, ( iii ) RMP coil geometries and ( iv ) perturbed magnetic field spectra. To this end, a unique set of in-vessel RMP coils is being designed and, in this work, their conceptual design is presented. This unique set of coils is composed of three toroidal arrays of coils on the low field side and three toroidal arrays of coils on the high field side. Each of these six toroidal arrays is composed of 18 coils thus allowing for the creation of RMP fields with toroidal mode numbers n ≤ 9 and with increased control of the poloidal mode number spectrum. To study dynamical effects of RMP fields of different toroidal mode numbers, all rotating simultaneously with different velocities, each of the 108 RMP coils will be powered independently by power supplies that can provide voltages of up to 4 kV and electric currents of up to 2 kA, with frequencies varying continuously from 0 Hz up to 10 kHz. A set of physical criteria were used to determine the optimal coil geometry and their respective number of turns to reduce the coil currents and voltages during operation with alternate current. The conceptual design was carried out using both the vacuum approach (no plasma response) and the single-fluid response approach, which accounts for the response of a linear, single-fluid, visco-resistive plasma calculated using the M3D-C 1 code. • Design of RMP coils. • Plasma response to externally applied magnetic perturbations. • ELM control by RMP fields with n t o r ≤ 9 . • Application of RMP fields from both LFS and HFS.

Fusion Engineering and DesignVol. 211
University of San Diego (US), Rensselaer Polytechnic Institute (US), Universidade de São Paulo (BR), University of Michigan (US), Princeton Plasma Physics Laboratory (US), University of California San Diego (US), Institute of Physics of the Slovak Academy of Sciences (SK), École Polytechnique Fédérale de Lausanne (CH)
Fundação de Amparo à Pesquisa do Estado de São Paulo, Conselho Nacional de Desenvolvimento Científico e Tecnológico
Affordable and clean energy
Openalex Percentile: Top 16%
Magnetic confinement fusion research
1.87
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