Персона: Харьков, Максим Михайлович
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SURFACE MODIFICATIONS OF W-BASED MATERIALS UNDER HELIUM AND DEUTERIUM ION IMPLANTATION
2021, Ogorodnikova, O. V., Klimov, N. S., Gasparyan, Yu. M., Harutyunyan, Z. R., Efimov, V. S., Kovalenko, D., Gutarov, K., Poskakalov, А. G., Kharkov, M. M., Kaziev, A. V., Харьков, Максим Михайлович, Гаспарян, Юрий Микаэлович, Казиев, Андрей Викторович, Ефимов, Виталий Сергеевич, Огородникова, Ольга Вячеславовна
In a thermonuclear reactor, materials will be irradiated with hydrogen isotopes and helium (He), neutrons, and heat fluxes. Tungsten (W) and dense nano-structured tungsten (CMSII) coatings are used as plasma-facing materials in current tokamaks and suggested to be used for future fusion devices. In this regard, the study of the accumulation of He and deuterium (D) in W based materials and corresponding surface modifications under normal operation conditions and transient events appears necessary for assessment of safety of fusion reactor due to the radioactivity of tritium and material performance and for the plasma fuel balance. Therefore, in this work, irradiation of W-based materials with D and He ions in stationary regime and in quasi-stationary high-current plasma gun QSPA-T below and above the melting threshold has been performed. In QSPA-T, a pulse duration was 1 ms and number of pulses was varied from one to thirty. In stationary plasma loads, ion energy was varied from 20 to 3 keV, temperature 300-1200 K and flux/fluence 1017-1021 at/m2s/1020-1025 at/m2.