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Information × Registration Number 0126U000655, R & D request Title Research into the properties of plasma in toroidal fusion plants, discharges for treating the walls of vacuum chambers, and development of advanced methods for diagnosing plasma and the condition of vacuum surfaces. Head Ihor Y. Harkusha, Доктор фізико-математичних наукVolodymyr Y. Moiseenko, Доктор фізико-математичних наук Registration Date 23-01-2026 Organization National Science Center "Kharkiv Institute of Physics and Technology" popup.description1 Plasma stability will be studied to understand the fundamental mechanisms that affect the efficiency of plasma confinement in stellarators and tokamaks. Comparison of the plasma stability of the U-2M stellarator with data from other facilities (JET, MAST-U, TCV, ASDEX-U, W7-X, TJ-II, LHD) will allow us to identify the main features of plasma confinement in ITER and DEMO. The work is aimed at studying plasma instabilities that significantly affect the efficiency of a future fusion reactor. The study of plasma instabilities, in particular large-scale plasma oscillations of stellarators, is being conducted at the flagship of stellarator research, the Wendelstein 7-X stellarator, as part of international cooperation under the EUROfusion program. The Wendelstein 7-X (W7-X) stellarator was designed to remain MHD-stable up to a volume-averaged beta plasma <β> of ~4%–5%. To verify that the optimization criteria are met, it is crucial to analyze and understand any MHD mode activity in the device. Our research will provide additional data for this program, which is why it is relevant. The goal is also to develop and improve scenarios for creating plasma by discharges in the ion cyclotron frequency range for further use in modern stellarators and tokamaks, in particular the Wendelstein 7-X stellarator. In addition to practical benefits, this will contribute to the deepening of knowledge in the physics of radio frequency plasma creation, with the key role of experiments on the Uragan-2M stellarator. The main goal of the work is to develop scenarios for cleaning the vacuum surfaces of toroidal chambers of fusion devices using various types of discharges, which can be used in large superconducting toroidal fusion devices in the EUROfusion program. And which will have high efficiency. The goal of modernizing and expanding the plasma diagnostics installed on the U-2M stellarator is to obtain more reliable and detailed experimental information about the operation of this device. popup.nrat_date 2026-01-23 Close