Nikolay M. Kartsev

Nikolay M. Kartsev


Research Focus & Metrics

Academic Career Length

14Years (2013-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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29 December 2021 in Fusion Engineering and Design
Verified
Journal Article
Closed access
YMYuri V Mitrishkin
Yuri V Mitrishkin
PKP.S. Korenev
P.S. Korenev
AKArtem Konkov
Artem Konkov
NKNikolay M. Kartsev
Nikolay M. Kartsev
ISI.S. Smirnov
I.S. Smirnov

17 April 2019 in Control Engineering Practice
Verified
Journal Article
Closed access
Yuri V MitrishkinYuri V Mitrishkin
Yuri V Mitrishkin
PKPavel Korenev
Pavel Korenev
NKNikolay M. Kartsev
Nikolay M. Kartsev
EKEvgeniy A. Kuznetsov
Evgeniy A. Kuznetsov
APArtem A. Prokhorov
Artem A. Prokhorov
MPMikhail I. Patrov
Mikhail I. Patrov

1 January 2013 in IFAC Proceedings Volumes
Verified
Journal Article
Closed access
PDF file
YMYuri V Mitrishkin
Yuri V Mitrishkin
NKNikolay M. Kartsev
Nikolay M. Kartsev
SZSemjon M. Zenckov
Semjon M. Zenckov

1 April 2022 in Automation and Remote Control
Verified
Journal Article
Closed access
PDF file
Yuri V MitrishkinYuri V Mitrishkin
Yuri V Mitrishkin
PKP. S. Korenev
P. S. Korenev
AKArtem Konkov
Artem Konkov
NKNikolay M. Kartsev
Nikolay M. Kartsev
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.