2021_Взаимодействие ионов с поверхностью (ВИП)
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- ПубликацияОткрытый доступВРЕМЯ-РАЗРЕШЕННАЯ ФОТОЛЮМИНЕСЦЕНЦИЯ Al2O3, ОБЛУЧЕННОГО ТЯЖЕЛЫМИ ИОНАМИ С ЭНЕРГИЕЙ 1.2 – 3 МэВ/АЕМ(НИЯУ МИФИ, 2021) Маматова, М.; Скуратов, В. А.; Олейничак, А.; Даулетбекова, А. К.; Гиниятова, Ш. Г.; Скуратов, Владимир АлексеевичTime Correlated Single Photon Counting technique has been used to study the luminescence decay in Al2O3 irradiated with swift heavy ions. As was found, picosecond laser pulse excitation at 445 nm enhances broad overlapped emission bands ranging from 490 to 750 nm with lifetimes gradually increasing from 7 ns (500 nm) to τ = 9 ns (640 nm). The nature of this luminescence is associated with radiative recombination of F2 2+-centers and F2 2+-centers + Cr impurity.
- ПубликацияОткрытый доступАМОРФИЗАЦИЯ И МЕХАНИЧЕСКИЕ НАПРЯЖЕНИЯ В Si3N4 ПРИ ОБЛУЧЕНИИ БЫСТРЫМИ ТЯЖЕЛЫМИ ИОНАМИ(НИЯУ МИФИ, 2021) Мутали, А. К.; Скуратов, В. А.; Ибраева, А. Д.; Жумажанова, А. Т.; Даулетбекова, А.; Акылбеков, А.; Здоровец, М. В.; Скуратов, Владимир АлексеевичThe Raman spectroscopy method was used to study the radiation damage and associated internal mechanical stresses in polycrystalline silicon nitride (Si3N4) irradiated with swift heavy 167 MeV Xe and 710 MeV Bi ions. The cross-section and near surface spectra of the irradiated region were registered at room temperature. FWHM parameters - 204 cm−1 and peak position - 862 cm−1 were used to characterize the amorphization and the mechanical stress level.
- ПубликацияОткрытый доступВЛИЯНИЕ ГЕЛИЯ НА НАКОПЛЕНИЕ ДЕЙТЕРИЯ В СООСАЖДЕННЫХ ВОЛЬФРАМОВЫХ ПЛЁНКАХ(НИЯУ МИФИ, 2021) Крат, С. А.; Фефелова, Е. А.; Пришвицын, А. С.; Гаспарян, Ю. М.; Писарев, А. А.; Гаспарян, Юрий Микаэлович; Пришвицын, Александр Сергеевич; Крат, Степан АндреевичВ ИТЭР в качестве топлива будет использоваться дейтерий-тритиевая смесь, накопление радиоактивного трития в материалах стенки реактора представляет проблему с точки зрения радиационной безопасности. Одним из основных механизмов накопления изотопов водорода в реакторе является соосаждение с материалами обращенных к плазме элементов (ОПЭ) [1,2]. В ИТЭР в качестве материала наиболее нагруженной области первой стенки – дивертора, выбран вольфрам. Понимание процесса соосаждения изотопов водорода с этим металлом необходимо для количественной оценки удержания трития в ОПЭ.
- ПубликацияОткрытый доступРАСПЫЛЕНИЕ И ФОРМИРОВАНИЕ ПОРИСТОГО СЛОЯ В ГРАФИТЕ ПРИ ВЫСОКОТЕМПЕРАТУРНОМ ИОННОМ ОБЛУЧЕНИИ(НИЯУ МИФИ, 2021) Пунтаков, Н. А.; Беграмбеков, Л. Б.; Долганов, Г. Д.; Грунин, А. В.; Беграмбеков, Леон Богданович; Пунтаков, Николай АлексеевичThe paper investigates the features of sputtering, formation and development of a nearsurface porous layer in fine-grained isotropic graphite depending on the irradiation current density, irradiation fluence, temperature and thickness of the irradiating sample. The samples were irradiated with accelerated ions of deuterium, hydrogen, and helium plasma. The influence of the growth of the porous layer on the rate of sputtering of the surface is discussed.
- ПубликацияОткрытый доступSURFACE MODIFICATIONS OF W-BASED MATERIALS UNDER HELIUM AND DEUTERIUM ION IMPLANTATION(НИЯУ МИФИ, 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 ВячеславовнаIn 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.
- ПубликацияОткрытый доступAPPLICATION OF LIBS, LA-QMS, LA-TOF-MS FOR FUSION RELEVANT MATERIALS ANALYSIS(НИЯУ МИФИ, 2021) Efimov, N. E.; Sinelnikov, D. N.; Bulgadaryan, D. G.; Gasparyan, Y. M.; Vovchenko, E. D.; Marenkov, E. D.; Маренков, Евгений Дмитриевич; Ефимов, Никита Евгеньевич; Вовченко, Евгений Дмитриевич; Синельников, Дмитрий Николаевич; Гаспарян, Юрий МикаэловичOne of the critical issues on the way to controlled nuclear fusion is related to plasma wall interaction. Such interaction leads to co-deposition of hydrogen isotopes together with eroded first wall materials. It is known that the deuterium-tritium (DT) mixture will be used in ITER and future fusion devices as a fuel. So as the accumulation of radioactive tritium in the machines is limited by the nuclear license, there is a need for some remote fuel retention monitoring system. In current devices, the total fuel amount is determined from the gas balance (difference between input and output flows) measurements and from a post mortem analysis of plasmafacing components. One of the most promising techniques which can be applied in situ in tokamaks is based on laser irradiation of the surface of interest followed by mass- or optical spectroscopy. Such a technique was already applied in TEXTOR tokamak to the hydrogenic carbon layers [1], and it is included in the task list of ITER with a high priority.
- ПубликацияОткрытый доступВЛИЯНИЕ УЛЬТРАФИОЛЕТОВОГО ИЗЛУЧЕНИЯ НА СОДЕРЖАНИЕ И ДЕСОРБЦИЮ ДЕЙТЕРИЯ ИЗ СООСАЖДЕННЫХ ЛИТИЕВЫХ СЛОЕВ(НИЯУ МИФИ, 2021) Хомяков, А. К.; Крат, С. А.; Пришвицын, А. С.; Фефёлова, Е. А.; Гаспарян, Ю. М.; Писарев, А. А.; Писарев, Александр Александрович; Пришвицын, Александр Сергеевич; Гаспарян, Юрий Микаэлович; Крат, Степан АндреевичThe influence of ultraviolet irradiation of co-deposited lithium layers on the content and desorption of deuterium from them is considered. It was found that exposure to ultraviolet radiation suppresses desorption at high temperatures, facilitates desorption at low temperatures. Effects are considered that can form the basis for the development of methods for determining the places of accumulation of lithium hydride in tokamaks with lithium walls, as well as facilitating the removal of heavy hydrogen isotopes from the walls of installations.
- ПубликацияОткрытый доступОЦЕНКА РАСПЫЛЕНИЯ ЭЛЕКТРОДОВ В МИНИАТЮРНОМ ЛИНЕЙНОМ УСКОРИТЕЛЕ(НИЯУ МИФИ, 2021) Каньшин, И. А.; Мамедов, Н. В.; Солодовников, А. А.; Ефимов, Н. Е.; Мамедов, Никита Вадимович; Ефимов, Никита ЕвгеньевичIn this paper estimation of the electrodes sputtering of the miniature linear accelerator (MLA) are presented. Also, the experimental area of the deposited metal layer on the insulator surface MLA are shown. The experimental dates are in good qualitatively agreement with the simulated ones.
- ПубликацияОткрытый доступЗАХВАТ И УДЕРЖАНИЕ ГАЗОВ В СЛОЯХ, ОБРАЗУЕМЫХ НА МЕТАЛЛАХ, ПРИ ПЛАЗМЕННОМ ОСАЖДЕНИИ АТОМОВ АЛЮМИНИЯ(НИЯУ МИФИ, 2021) Беграмбеков Л. Б.; Довганюк, С. С.; Рукина, Ю. Г.; Касимова, Н. Н.; Беграмбеков, Леон Богданович; Довганюк, Сергей СергеевичIn this work, a thermal desorption study of the formation and modification of layers formed by the deposition of aluminum atoms on the surface of tungsten, molybdenum, titanium, nickel, iron and stainless steel was carried out. The features of the capture of hydrogen during the formation of surface layers on various metals and the nature of its retention are revealed.
- ПубликацияОткрытый доступDeuterium trapping in co-deposited layers of ITER-relevant materials(НИЯУ МИФИ, 2021) Krat, S. A.; Prishvitsyn, A. S.; Vasina, Ya. A.; Fefelova, E. A.; Gasparyan, Yu. M.; Pisarev, A. A.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович; Крат, Степан Андреевич; Пришвицын, Александр СергеевичHydrogen isotope accumulation in fusion devices is a serious problem. Because deuterium-tritium mixture will be a working gas in future fusion devices, including ITER tokamak, tritium accumulation is an issue from the perspective of radiation safety. In total, only 700 grams of tritium are allowed to be present in ITER vessel at any time, with additional 120 in the cryopumps, and 180 grams allocated to measurement error, to the total of 1000 grams.
- ПубликацияОткрытый доступDust in tokamak and related safety open issues(НИЯУ МИФИ, 2021) Grisolia, С.During fusion machine operation and due to plasma wall interaction, particles/dust will be created (size ranging from nanometer to tens of micron). Different morphologies of dust are expected to be produced from spherical particles induced by melting of metal after high heat flux interactions (unipolar arcs, ELMs,...) to fractal ones created by accretion. The later point is confirmed by dust collection in a full tungsten (W) environment machine, the WEST tokamak. Indeed, among the collected particles, spherical and complex shape submicron-sized ones are found. Their high specific surface area can be associated with high physico-chemical reactivity.
- ПубликацияОткрытый доступCOMPARISON OF DEUTERIUM RETENTION IN TUNGSTEN AND WCrY ALLOY IN THE PRESENCE OF HELIUM(НИЯУ МИФИ, 2021) Harutyunyan, Z.; Gasparyan, Yu.; Pisarev, A.; Litnovsky, A.; Klein, F.; Linsmeier, Ch.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович; Арутюнян, Зорий РобертовичDuring operation of the future fusion power plant, the plasma-facing components (PFC) will be exposed to intense fluxes of particles of deuterium, tritium, helium, as well as neutrons arising in the process of the D–T fusion reaction. In this regard, one of the important challenges is to minimize the accumulation of radioactive tritium in the PFC [1, 2], as well as to study the effect on the accumulation of helium impurities in the plasma.