A simple model to evaluate the heat flux onto the EU-DEMO plasma facing components during the current quench

Abstract A model for the plasma evolution during the current quench is presented in this paper: it allows to simulate the evolution of the phenomenon, carry on parametric studies and calculate the heat loads on the tokamak first wall. During the disruption of a tokamak plasma, the current decay rate, the dissipation of the magnetic energy, the repartition of the dissipated energy in different channels, the magnitude of the halo current and the width of the halo region are all functions of the plasma temperature and of the impurity densities. The energy balance equation determines the whole disruption evolution and it must be solved during the current quench, in the close flux surface region and in the halo.

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Publication Details

Journal
Nuclear Fusion
Published
2025-05-09
DOI
https://doi.org/10.1088/1741-4326/add675
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

A simple model to evaluate the heat flux onto the EU-DEMO plasma facing components during the current quench

M. Siccinio, T. Pütterich, E. Fable, Gabriella Pautasso et al.
Nuclear Fusion
Magnetic confinement fusion research
article

A simple model to evaluate the heat flux onto the EU-DEMO plasma facing components during the current quench

M. Siccinio, T. Pütterich, E. Fable, Gabriella Pautasso, F. Maviglia
article en

Abstract

Abstract A model for the plasma evolution during the current quench is presented in this paper: it allows to simulate the evolution of the phenomenon, carry on parametric studies and calculate the heat loads on the tokamak first wall. During the disruption of a tokamak plasma, the current decay rate, the dissipation of the magnetic energy, the repartition of the dissipated energy in different channels, the magnitude of the halo current and the width of the halo region are all functions of the plasma temperature and of the impurity densities. The energy balance equation determines the whole disruption evolution and it must be solved during the current quench, in the close flux surface region and in the halo.

Nuclear FusionVol. 65(6)
National Agency for New Technologies, Energy and Sustainable Economic Development (IT), Max Planck Institute for Plasma Physics (DE)
EUROfusion, European Commission, Euratom Research and Training Programme
Openalex Percentile: Top 95%
Magnetic confinement fusion research
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