<i>P</i> <sub>sep</sub>/<i>P</i> <sub>LH</sub> control in deuterium and deuterium–tritium JET plasmas

Abstract The high confinement mode (H-mode) is a promising route to achieve high performance tokamak operations, as the ones foreseen in ITER and beyond. However, accessing a stable H-mode phase requires that the power across the plasma separatrix, P sep , exceeds a certain power threshold, P LH . Feedback control can be utilized in this context to guide the H-mode entry and exit, and to tailor its evolution throughout the pulse by monitoring f Net LH defined as the ratio of P sep over P LH . Such a controller has been integrated into the JET plasma control system, using the neutral beam power and the gas puffing as actuators. In this work, we document successful P sep / P LH control studies carried out in deuterium and deuterium–tritium plasmas, which pave the way for using this portable controller in ITER and next step fusion devices.

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Publication Details

Journal
Plasma Physics and Controlled Fusion
Published
2025-04-03
DOI
https://doi.org/10.1088/1361-6587/adc8d0
Citations
2
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
3.74
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article

P sep/P LH control in deuterium and deuterium–tritium JET plasmas

A. Pau, A. Chomiczewska, E.R. Solano, D. Valcárcel et al.
2 citations
Plasma Physics and Controlled Fusion
Magnetic confinement fusion research
3.74
article

P sep/P LH control in deuterium and deuterium–tritium JET plasmas

A. Pau, A. Chomiczewska, E.R. Solano, D. Valcárcel, M. Lennholm, O. Sauter, S. Aleiferis, P. Carvalho, L. Piron, M. Baruzzo, Piero Martín, Кирил Киров
article en
2 citations

Abstract

Abstract The high confinement mode (H-mode) is a promising route to achieve high performance tokamak operations, as the ones foreseen in ITER and beyond. However, accessing a stable H-mode phase requires that the power across the plasma separatrix, P sep , exceeds a certain power threshold, P LH . Feedback control can be utilized in this context to guide the H-mode entry and exit, and to tailor its evolution throughout the pulse by monitoring f Net LH defined as the ratio of P sep over P LH . Such a controller has been integrated into the JET plasma control system, using the neutral beam power and the gas puffing as actuators. In this work, we document successful P sep / P LH control studies carried out in deuterium and deuterium–tritium plasmas, which pave the way for using this portable controller in ITER and next step fusion devices.

Plasma Physics and Controlled FusionVol. 67(5)
University of Padua (IT), Culham Science Centre (GB), Institute of Plasma Physics and Laser Microfusion (PL), Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati (IT), United Kingdom Atomic Energy Authority (GB), École Polytechnique Fédérale de Lausanne (CH)
Openalex Percentile: Top 9%
Magnetic confinement fusion research
3.74
DOISourceOpenAlex
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<i>P</i> <sub>sep</sub>/<i>P</i> <sub>LH</sub> control in deuterium and deuterium–tritium JET plasmas — A. Pau, A. Chomiczewska, et al. · Plasma Physics and Controlled Fusion (2025) | TGRS Research Map | TGRS