2023_Взаимодействие ионов с поверхностью (ВИП)

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Просмотр 2023_Взаимодействие ионов с поверхностью (ВИП) по Автор "Harutyunyan, Z. R."

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    QUANTITATIVE ANALYSIS OF THE TEMPERATURE DRIVEN CHROMIUM SEGREGATION IN W-Cr-Y ALLOY BY LOW ENERGY ION SCATTERING SPECTROSCOPY
    (НИЯУ МИФИ, 2023) Efimov, N. E.; Sinelnikov, D. N.; Wang, Y.; Harutyunyan, Z. R.; Gasparyan, Y. M.; Grishaev, M. V.; Nikitin, I. A.; Tan, X.; Синельников, Дмитрий Николаевич; Ефимов, Никита Евгеньевич; Арутюнян, Зорий Робертович; Никитин, Иван Андреевич; Гаспарян, Юрий Микаэлович; Гришаев, Максим Валерьевич
    One of the challenging problems which arise in the controlled nuclear fusion is related to the design and material choice of plasma facing components for the future reactors. Tungsten is considered to be one of the most suitable candidates due to its high melting point, thermal conductivity and relatively low erosion rate, and, therefore, it is planned to be used in nextgen facilities like ITER and DEMO. However, under high neutron fluxes its stable isotopes may form radioactive ones. Being not so hazardous while it is inside the reactor, in case of a loss of coolant accident (LOCA) a volatile oxide of W and of its transmutation products may appear, which is undesirable. A possible solution to avoid the release of the radioactive oxides is the use of self-passivating W-Cr-Y alloys [1], which under LOCA scenarios forms on the surface a chromium oxide, preventing the formation of tungsten oxide. Such alloys are of the great interest now, especially when it comes to analyzing the dynamics of the chromium release to the outermost layers [2,3]. In this work, capabilities of low energy ion scattering spectroscopy (LEIS) with small angle scattering to the characterization the surface morphology of W-11,4Cr-0,6Y after pre-annealing at different temperatures are revealed.