The feasibility of the L-H transition for a purely electron-heated EU-DEMO tokamak

Abstract We study numerically the feasibility of achieving the L-H transition in the current EU-DEMO tokamak baseline using uniquely direct electron heating. The ASTRA code coupled to the TGLF turbulent transport model is used to predict steady-state kinetic plasma profiles for diverse numerical scans. Among them, we have varied the separatrix electron density, the total amount of ECRH power, the microwave beam deposition profile and the plasma impurity content. The solutions are then compared to L-H transition scaling laws to assess whether the found plasma state would enter into H-mode. We find the plasma density and impurity content to be the key variables setting the boundaries in parameter space where the L-H transition is feasible. When impurities can be controlled under a certain threshold, given here for a fully shaped DEMO plasma, the L-H transition is achieved in all the studied conditions.

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Publication Details

Journal
Nuclear Fusion
Published
2024-09-27
DOI
https://doi.org/10.1088/1741-4326/ad7612
Citations
3
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.98

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article

The feasibility of the L-H transition for a purely electron-heated EU-DEMO tokamak

G. Tardini, M. Siccinio, H. Zohm, G. Suárez López et al.
3 citations
Nuclear Fusion
Magnetic confinement fusion research
1.98
article

The feasibility of the L-H transition for a purely electron-heated EU-DEMO tokamak

G. Tardini, M. Siccinio, H. Zohm, G. Suárez López, E. Fable
article en
3 citations

Abstract

Abstract We study numerically the feasibility of achieving the L-H transition in the current EU-DEMO tokamak baseline using uniquely direct electron heating. The ASTRA code coupled to the TGLF turbulent transport model is used to predict steady-state kinetic plasma profiles for diverse numerical scans. Among them, we have varied the separatrix electron density, the total amount of ECRH power, the microwave beam deposition profile and the plasma impurity content. The solutions are then compared to L-H transition scaling laws to assess whether the found plasma state would enter into H-mode. We find the plasma density and impurity content to be the key variables setting the boundaries in parameter space where the L-H transition is feasible. When impurities can be controlled under a certain threshold, given here for a fully shaped DEMO plasma, the L-H transition is achieved in all the studied conditions.

Nuclear FusionVol. 64(12)
Max Planck Institute for Plasma Physics (DE), Isotopen Technologien München (Germany) (DE), Ludwig-Maximilians-Universität München (DE)
EUROfusion
Openalex Percentile: Top 9%
Magnetic confinement fusion research
1.98
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