Improvement of plasma discharge performance at KTM tokamak
Chektybayev B. Tazhibayeva I. Batyrbekov E. Kashikbayev Y. Olkhovik D. Zarva D. Zhunisbek S. Duisen A. Zhaksybayeva A. Lee A. Pavlov V. Dokuka V. Khayrutdinov R.
November 2024Elsevier Ltd
Fusion Engineering and Design
2024#208
The paper presents the results of experimental campaigns conducted in 2022–2023 aimed at improving and enhancing plasma discharge parameters at the KTM tokamak. The experiments achieved a plasma current of approximately 500 kA in a limiter configuration, with a discharge duration of up to 2 s. Plasma discharges were obtained in the ohmic heating mode. The results described in the paper represent the next step toward achieving the plasma discharge design parameters for the KTM.
Experimental data , KTM tokamak , Modelling , Ohmic heating mode , Plasma control system , Plasma discharges
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Branch Institute of Atomic Energy of National Nuclear Center, Kurchatov, 180010, Kazakhstan
Shakarim University, Semey, Kazakhstan
National Nuclear Center of the Republic of Kazakhstan, Kurchatov, 180010, Kazakhstan
Tomsk Polytechnic University, Tomsk, 634050, Russian Federation
NRC «Kurchatov Institute», Moscow, Russian Federation
Branch Institute of Atomic Energy of National Nuclear Center
Shakarim University
National Nuclear Center of the Republic of Kazakhstan
Tomsk Polytechnic University
NRC «Kurchatov Institute»
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