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Real-time feedback control of the impurity emission front in tokamak divertor plasmas

Author

Listed:
  • T. Ravensbergen

    (DIFFER - Dutch Institute for Fundamental Energy Research
    Eindhoven University of Technology)

  • M. Berkel

    (DIFFER - Dutch Institute for Fundamental Energy Research)

  • A. Perek

    (DIFFER - Dutch Institute for Fundamental Energy Research
    École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • C. Galperti

    (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • B. P. Duval

    (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • O. Février

    (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • R. J. R. Kampen

    (DIFFER - Dutch Institute for Fundamental Energy Research
    Eindhoven University of Technology)

  • F. Felici

    (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • J. T. Lammers

    (Eindhoven University of Technology)

  • C. Theiler

    (École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))

  • J. Schoukens

    (Vrije Universiteit Brussel
    Eindhoven University of Technology)

  • B. Linehan

    (Plasma Science and Fusion Center, Massachusetts Institute of Technology)

  • M. Komm

    (Institute of Plasma Physics of the CAS)

  • S. Henderson

    (CCFE, Culham Science Centre, Abingdon)

  • D. Brida

    (Max-Planck-Institut für Plasmaphysik)

  • M. R. Baar

    (DIFFER - Dutch Institute for Fundamental Energy Research
    Eindhoven University of Technology)

Abstract

In magnetic confinement thermonuclear fusion the exhaust of heat and particles from the core remains a major challenge. Heat and particles leaving the core are transported via open magnetic field lines to a region of the reactor wall, called the divertor. Unabated, the heat and particle fluxes may become intolerable and damage the divertor. Controlled ‘plasma detachment’, a regime characterized by both a large reduction in plasma pressure and temperature at the divertor target, is required to reduce fluxes onto the divertor. Here we report a systematic approach towards achieving this critical need through feedback control of impurity emission front locations and its experimental demonstration. Our approach comprises a combination of real-time plasma diagnostic utilization, dynamic characterization of the plasma in proximity to the divertor, and efficient, reliable offline feedback controller design.

Suggested Citation

  • T. Ravensbergen & M. Berkel & A. Perek & C. Galperti & B. P. Duval & O. Février & R. J. R. Kampen & F. Felici & J. T. Lammers & C. Theiler & J. Schoukens & B. Linehan & M. Komm & S. Henderson & D. Bri, 2021. "Real-time feedback control of the impurity emission front in tokamak divertor plasmas," Nature Communications, Nature, vol. 12(1), pages 1-9, December.
    • Handle: RePEc:nat:natcom:v:12:y:2021:i:1:d:10.1038_s41467-021-21268-3
    DOI: 10.1038/s41467-021-21268-3
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    Cited by:

    1. Zhenyang Li & Shiyuan Liu & Yanhui Pu & Gang Huang & Yingbo Yuan & Ruiqi Zhu & Xufeng Li & Chunyan Chen & Gao Deng & Haihan Zou & Peng Yi & Ming Fang & Xin Sun & Junzhe He & He Cai & Jiaxiang Shang & , 2023. "Single-crystal ZrCo nanoparticle for advanced hydrogen and H-isotope storage," Nature Communications, Nature, vol. 14(1), pages 1-10, December.

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