Abstract
Ensuring the stability of the vertical position of plasma is a paramount task of magnetic control for modern D-shaped tokamaks. The introduction of an additional horizontal field coil located near the vacuum vessel provides more than an order of magnitude larger vertical controllability domain than the use of a pair of P6&P12 poloidal field coils in the IGNITOR tokamak project. Two robust systems for controlling the vertical position of plasma are synthesized by the \( H_\infty \)-optimization theory method and by tuning PID controllers in a cascade system by the method of linear matrix inequalities. The results of mathematical modeling of control systems show that the modernization of the poloidal system of the IGNITOR tokamak project leads to an increase in the stability margin of the plasma vertical position control system, the quality of control when rejecting disturbances, and the reliability of the tokamak.
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ACKNOWLEDGMENTS
The authors would like to thank the employees of SSC RF “Troitsk Institute of Innovative and Thermonuclear Research” (TRINITY) Doctor (Phys.-Math.) Sciences N.B. Rodionov and Cand. (Phys.-Math.) Sciences V.N. Dokuka for useful discussions and data provided on the IGNITOR tokamak.
Funding
This work was supported by the Russian Science Foundation,project no. 21-79-20180, the Russian Foundation for Basic Research, project no. 19-31-90136, and was also partially funded by SSC RF TRINITY (Troitsk).
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Translated by V. Potapchouck
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Mitrishkin, Y.V., Korenev, P.S., Konkov, A.E. et al. Suppression of Vertical Plasma Displacements by Control System of Plasma Unstable Vertical Position in D-Shaped Tokamak. Autom Remote Control 83, 579–599 (2022). https://doi.org/10.1134/S0005117922040051
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DOI: https://doi.org/10.1134/S0005117922040051