RUS  ENG
Full version
JOURNALS // Problemy Upravleniya // Archive

Probl. Upr., 2019 Issue 4, Pages 15–26 (Mi pu1146)

This article is cited in 1 paper

Reviews

Plasma control in tokamaks. Part 3.2. Simulation and realization of plasma control systems in ITER and constructions of DEMO

Yu. V. Mitrishkinab, N. M. Kartsevb, A. E. Konkovab, M. I. Patrovc

a Lomonosov Moscow State University, Russia
b V.A. Trapeznikov Institute of Control Sciences of Russian Academy of Sciences, Moscow, Russia
c Ioffe Institute of Russian Academy of Sciences, Saint-Petersburg, Russia

Abstract: Experimental testing of ITER scenarios on DIII-D (US) and WEST (France) tokamaks, approaches to simulation and realization of plasma control systems in ITER, preparation of ITER plasma control systems for starting and exploitation are presented. The road maps, which are known in Europe, for development and creation of the first fusion power plant DEMO (the next step after ITER) are shown. These maps give two directions of DEMO development: (i) conventional tokamaks with relatively large aspect ratio and (ii) spherical tokamaks of modular type allowing to notably reduce the time of DEMO creation and to get competitive cheap electrical energy. The basic trends in DEMO poloidal systems design are given, and the initial version of DEMO plasma vertical position control system is presented.

Keywords: tokamak, plasma, plasma magnetic control, ITER, DEMO constructions.

UDC: 681.51;621.3.002.5;621.039.6;533.95

Received: 22.01.2019
Revised: 25.02.2019
Accepted: 05.03.2019

DOI: 10.25728/pu.2019.4.2



© Steklov Math. Inst. of RAS, 2024