Plasma Control in Tokamaks Part 3.2. Simulation and Realization of Plasma Control Systems in ITER and Constructions of DEMO

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Yuri Vladimirovich Mitrishkin
Nikolay Mikhailovich Kartsev
Artem Evgenyevich Konkov
Mikhail Ivanovich Patrov


Experimental testing of ITER scenarios on the DIII-D (US) and WEST (France) tokamaks, approaches for simulation and realization of ITER plasma control systems, the preparation of ITER plasma control systems for starting and exploitation are presented. The roadmaps that are known in Europe for the development and creation of the first fusion power plant DEMO (the next step after ITER) are reported. These maps show two directions of DEMO development: (i) based on conventional tokamaks with relatively large aspect ratio and (ii) based on spherical tokamaks of module type giving a chance to noticeably reduce the time needed to create the DEMO and to get cheap competitive electrical energy. The basic trends in the design of DEMO poloidal systems, as well as the initial version of the DEMO plasma vertical position control system, are given.


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How to Cite
Mitrishkin, Y., Kartsev, N., Konkov, A., & Patrov, M. (2020). Plasma Control in Tokamaks. Advances in Systems Science and Applications, 20(3), 136-152.
Author Biographies

Nikolay Mikhailovich Kartsev, V.A. Trapeznikov Institute of Control Sciences of Russian Academy of Sciences

System Identification Lab, candidate of engineering sciences

Artem Evgenyevich Konkov, V.A. Trapeznikov Institute of Control Sciences of Russian Academy of Sciences

Systems Identification Lab, mathematician

Mikhail Ivanovich Patrov, A.F. Ioffe Institute of Russian Academy of Sciences

Globus-M2 tokamak team, researcher