CarMa0NL modelling of COMPASS halo currents

Abstract A vertical displacement event in the COMPASS tokamak is modelled using the CarMa0NL code, with the halo-current width treated as a free parameter. The simulations that best reproduce the experimental evolution are those in which the resulting safety factor at the last closed flux surface remains above unity. This result is consistent with the possibility that the interaction of the \(m/n=1/1\) mode with higher harmonics, and the associated formation of a stochastic magnetic field-line structure, may contribute to setting the halo-current width. The potential relevance of this observation to scrape-off-layer widening and divertor heat-load mitigation during normal operation is discussed.

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Publication Details

Journal
Nuclear Fusion
Published
2026-10-29
DOI
https://doi.org/10.1088/1741-4326/aebb49
Primary Topic
Magnetic confinement fusion research
Type
article
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article

CarMa0NL modelling of COMPASS halo currents

David Tskhakaya, Vadim Yanovskiy, J. Havlíček, Roberto Paccagnella et al.
Nuclear Fusion
Magnetic confinement fusion research
article

CarMa0NL modelling of COMPASS halo currents

David Tskhakaya, Vadim Yanovskiy, J. Havlíček, Roberto Paccagnella, Vladimir D. PUSTOVITOV, F. Villone, A. Casolari, Antonio Iaiunese, M. Zuin, N. Isernia, Alberto Loarte, Ekaterina Matveeva
article en

Abstract

Abstract A vertical displacement event in the COMPASS tokamak is modelled using the CarMa0NL code, with the halo-current width treated as a free parameter. The simulations that best reproduce the experimental evolution are those in which the resulting safety factor at the last closed flux surface remains above unity. This result is consistent with the possibility that the interaction of the \(m/n=1/1\) mode with higher harmonics, and the associated formation of a stochastic magnetic field-line structure, may contribute to setting the halo-current width. The potential relevance of this observation to scrape-off-layer widening and divertor heat-load mitigation during normal operation is discussed.

Nuclear Fusion
ITER (FR), National Agency for New Technologies, Energy and Sustainable Economic Development (IT), Universität Innsbruck (AT), Czech Academy of Sciences (CZ), Kurchatov Institute (RU), Czech Academy of Sciences, Czech Language Institute (CZ), Czech Academy of Sciences, Institute of Plasma Physics (CZ), University of Naples Federico II (IT)
Openalex Percentile: Top 18%
Magnetic confinement fusion research
DOIOpen Access PDFOpenAlex
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CarMa0NL modelling of COMPASS halo currents — David Tskhakaya, Vadim Yanovskiy, et al. · Nuclear Fusion (2026) | TGRS Research Map | TGRS