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

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. Brida and M. R. Baar
Additional contact information
T. Ravensbergen: DIFFER - Dutch Institute for Fundamental Energy Research
M. Berkel: DIFFER - Dutch Institute for Fundamental Energy Research
A. Perek: DIFFER - Dutch Institute for Fundamental Energy Research
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
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
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

Nature Communications, 2021, vol. 12, issue 1, 1-9

Abstract: 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.

Date: 2021
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DOI: 10.1038/s41467-021-21268-3

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