Machine learning prediction of plasma behavior from discharge configurations on WEST

Abstract Accurately predicting plasma behavior based on discharge configurations is essential for the safe and efficient operation of tokamak experiments. While physics-based integrated modeling codes provide valuable insights, their high computational cost limits their applicability for fast scenario design and control optimization. In this study, we propose a transformer-based machine learning model to predict key global plasma parameters on the Tungsten (W) Environment in Steady-State Tokamak (WEST) tokamak, including the normalized beta ( β n ), toroidal beta ( β t ), poloidal beta ( β p ), plasma stored energy ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>W</mml:mi> <mml:mrow> <mml:mrow> <mml:mi>mhd</mml:mi> </mml:mrow> </mml:mrow> </mml:msub> </mml:mrow> </mml:math> ), safety factor at the magnetic axis ( q 0 ), and safety factor at the 95% flux surface ( q 95 ). The model uses only signals that can be defined before the discharge, such as magnetic coil currents, auxiliary heating power, plasma current reference, and line-averaged plasma density. Trained on 550 discharges from the WEST campaigns, the model demonstrates an average mean square error (MSE) loss of 0.026, an average coefficient of determination R 2 of 0.94, and achieves inference times on the order of 0.1 s. These results highlight the potential of data-driven surrogate models for assisting in discharge planning, scenario evaluation, and real-time control of tokamak plasmas.

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Publication Details

Journal
Nuclear Fusion
Published
2026-02-24
DOI
https://doi.org/10.1088/1741-4326/ae4917
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
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article

Machine learning prediction of plasma behavior from discharge configurations on WEST

R Varennes, Zhisong Qu, W X Team, Kyungtak Lim et al.
Nuclear Fusion
Magnetic confinement fusion research
article

Machine learning prediction of plasma behavior from discharge configurations on WEST

R Varennes, Zhisong Qu, W X Team, Kyungtak Lim, Weidong Chen, P. Moreau, Xavier Garbet, Chenguang Wan, Remy Nouailletas, Kunpeng Li, Jiangang Li, Jia Huang, YoungWoo Cho
article en

Abstract

Abstract Accurately predicting plasma behavior based on discharge configurations is essential for the safe and efficient operation of tokamak experiments. While physics-based integrated modeling codes provide valuable insights, their high computational cost limits their applicability for fast scenario design and control optimization. In this study, we propose a transformer-based machine learning model to predict key global plasma parameters on the Tungsten (W) Environment in Steady-State Tokamak (WEST) tokamak, including the normalized beta ( β n ), toroidal beta ( β t ), poloidal beta ( β p ), plasma stored energy ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>W</mml:mi> <mml:mrow> <mml:mrow> <mml:mi>mhd</mml:mi> </mml:mrow> </mml:mrow> </mml:msub> </mml:mrow> </mml:math> ), safety factor at the magnetic axis ( q 0 ), and safety factor at the 95% flux surface ( q 95 ). The model uses only signals that can be defined before the discharge, such as magnetic coil currents, auxiliary heating power, plasma current reference, and line-averaged plasma density. Trained on 550 discharges from the WEST campaigns, the model demonstrates an average mean square error (MSE) loss of 0.026, an average coefficient of determination R 2 of 0.94, and achieves inference times on the order of 0.1 s. These results highlight the potential of data-driven surrogate models for assisting in discharge planning, scenario evaluation, and real-time control of tokamak plasmas.

Nuclear FusionVol. 66(4)
University of Science and Technology of China (CN), Nanyang Technological University (SG), Chinese Academy of Sciences (CN), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), Hefei Institutes of Physical Science (CN), CEA Cadarache (FR), Institute of Plasma Physics (CN)
Openalex Percentile: Top 43%
Magnetic confinement fusion research
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