Jul 2 – 6, 2018
Žofín Palace
Europe/Prague timezone

P4.1079 Robust plasma position, current, and shape control system simulated on plasma evolution code for the spherical tokamak Globus

Jul 5, 2018, 2:00 PM
2h
Mánes

Mánes

Speaker

Pavel Korenev

Description

See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P4.1079.pdf Robust plasma position, current, and shape control system simulated on plasma evolution code for the spherical tokamak Globus-M Y.V. Mitrishkin1,2, A.A. Prokhorov,1,2, P.S. Korenev1,2, M.I. Patrov3 1 Lomonosov Moscow State University, Faculty of Physics, Moscow, Russia 2 V.A. Trapeznikov Inst. of Control Sciences, Russian Academy of Sciences, Moscow, Russia 3 Ioffe Physical-Technical Inst. of the Russian Academy of Sciences, Saint Petersburg, Russia To simulate plasma shape and position during tokamak discharges a new plasma evolution code was developed in MATLAB. To obtain plasma position and coil currents the plasma motion equation, Faraday’s law equations for PF coils, vacuum vessel and plasma circuits are numerically solved with input voltages. Forces acting on plasma and inductance matrices are obtained from a plasma current density distribution, which is calculated to satisfy Grad-Shafranov equation. To design feedback controllers, linear plasma models were obtained on the Globus-M (Ioffe Inst.) experimental data. Then these controllers were applied on the developed plasma evolution code. The hierarchical multi-loop control system includes cascades for controlling the plasma position and current with robust SISO PID controllers tuned by QFT [1]. The outer cascade of plasma shape control incorporates a plasma reconstruction code, which is created on moving filaments and has sufficient accuracy and Fig. 1. Control process of the plasma shape: Br, Bz speed of response [2]. A plasma shape MIMO in X-point, δΨ1= ΨX‒Ψ1 , δΨ2= ΨX‒Ψ2 , ΨX is the flux at X-point, Ψ1, Ψ2 are fluxes at the separatrix. controller was designed by the H∞ robust loop-shaping approach [3] for magnetic field at X-point Br, Bz and poloidal fluxes on the plasma separatrix Ψ1, Ψ2. Full thyristor current inverter models operating in self-oscillation mode up to 3 kHz were used as original fast actuators for plasma position control [4]. The plasma shape controller is turned on at 0.18 s of the discharge and transfers the plasma boundary to the desired position in less than 5 ms during the divertor phase (Fig. 1). That is critically important due to comparatively short plasma discharges on the Globus-M tokamak of about 200-250 ms. [1] Garcia-Sanz M. Robust Contr. Eng.: Practical Quantitative Feedback Theory Solutions, CRC Press, 2017. [2] Mitrishkin Y.V., Prohorov A.A. Korenev P.S.et al. Proc. IFAC WC, Toulouse, France, pp. 11883-11888, 2017. [3] McFarlane D. and Glover K. IEEE Trans. Automatic Control, Vol. 37, No. 6, pp. 759-768, June 1992. th [4] Kuznetsov E.A., Mitrishkin Y.V., Yagnov V.A., and Shcherbitsky V.N. Proc. 11 IEEE Intern. Conf. AICT2017, Inst. of Control Sciences, September 20-22, 2017, Moscow, Russia, pp. 485-489, 2017.

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