Персона: Писарев, Александр Александрович
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Институт лазерных и плазменных технологий
Стратегическая цель Института ЛаПлаз – стать ведущей научной школой и ядром развития инноваций по лазерным, плазменным, радиационным и ускорительным технологиям, с уникальными образовательными программами, востребованными на российском и мировом рынке образовательных услуг.
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Александр Александрович
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- ПубликацияОткрытый доступСравнение удержания дейтерия в вольфрамовых пленках различной толщины(2024) Крат, С. А.; Пришвицын, А. С.; Сорокин, И. А.; Фефелова, Е. А.; Гаспарян, Ю. М.; Писарев, А. А.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович; Пришвицын, Александр Сергеевич; Крат, Степан Андреевич; Сорокин, Иван АлександровичПроведено сравнительное исследование содержание дейтерия в со-осажденных из плазмы магнетронного разряда на молибденовые подложки вольфрам-дейтериевых слоях толщиной 50, 250 и 750 нм. Измерения проводились методом in vacuo термодесорбционной спектроскопии без контакта с атмосферой. Проведено моделирование экспериментальных данных в коде ТМАР7, получены концентрации и энергии ловушек, при которых достигается наилучшее согласие с экспериментом. Содержание дейтерия в пленках, осажденных при температуре ~100°С, составило 3–5 ат. %. Показано, что толщина пленок не оказывает существенного влияния на характеристики центров захвата удержания дейтерия, хотя вид спектров для наиболее толстых пленок несколько отличается.
- ПубликацияОткрытый доступМатериалы и процессы получения теплозащитных покрытий(НИЯУ МИФИ, 2016) Попов, В. В.; Писарев, А. А.; Попов, Виктор Владимирович; Писарев, Александр АлександровичРассмотрены основные вопросы, связанные с созданием современных теплозащитных покрытий. Выполнен анализ используемых и перспективных керамических оксидных материалов для теплозащитных покрытий, методов их синтеза, способов нанесения теплозащитных покрытий, а также возможных механизмов их разрушения. Монография предназначена для широкого круга специалистов, аспирантов и студентов, занимающихся изучением материалов теплозащитных покрытий и созданием самих теплозащитных покрытий.
- ПубликацияОткрытый доступALUMINIUM OXIDATION IN PLASMA OF ABNORMAL GLOW DISCHARGE(НИЯУ МИФИ, 2023) Pisarev, A. A.; Tarasyuk, G. M.; Borisyuk, P. V.; Isaenkova, M. G.; Lebedinskii, Yu. Yu.; Zaripova, M. M.; Исаенкова, Маргарита Геннадьевна; Писарев, Александр Александрович; Тарасюк, Григорий Михайлович; Борисюк, Петр Викторович; Лебединский, Юрий ЮрьевичAluminum oxide layers in all its various forms have become widespread due to the unique combination of properties that can be modified by varying the conditions of their growth. The alumina layer can either be applied to the substrate by chemical and physical methods or grown by oxidation. For practical purposes, layers of various thicknesses and structures are needed. The standard method for obtaining thick (of the order of 100-1000 nm) porous layer is electric arc anodization in weak electrolytes. The standard method for obtaining thin (about 10 nm) layers is thermal oxidation. Dense layers of intermediate thickness are difficult to obtain by such methods. There are few papers in the literature that investigate the possibility of obtaining oxide layers with a thickness of tens of nanometers by oxidizing aluminum in oxygen plasma [1-5]. The description of the kinetics of the oxidation process in those works was given on the basis of the assumption of the diffusion character of oxygen transfer from the surface into the interior of the metal. This approach is absolutely unsuitable for description the transport of oxygen and aluminum through the oxide layer, since both oxygen and aluminum in the oxide are in the form of ions, and an electric charge is formed on the surface of the dielectric facing the plasma, so that the transport of oxygen coming from the plasma must occur under by the action of an electric field in the oxide dielectric layer. In this work, experiments on plasma enhanced oxidation (PEO) were carried out on the oxidation of aluminum in the anomalous glow discharge oxygen plasma, which provides uniform treatment over the entire surface of samples of arbitrary shape. Also, a simple model was proposed for description of the oxidation kinetics, taking into account oxygen transport in the electric field.
- 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 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 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.
- ПубликацияОткрытый доступHELIUM THERMAL DESORPTION FROM TUNGSTEN AFTER ION BEAM IRRADIATION AT ELEVATED TEMPERATURES(НИЯУ МИФИ, 2019) Ryabtsev, S. A.; Gasparyan, Yu. M.; Harutyunyan, Z. R.; Efimov, V. S.; Aksenova, A. S.; Pisarev, A. A.; Писарев, Александр Александрович; Ефимов, Виталий Сергеевич; Гаспарян, Юрий Микаэлович; Арутюнян, Зорий РобертовичHelium (He) is a product of deuterium-tritium reaction, so appearance of helium impurities will be unavoidable. In addition to He implantation from fusion plasma, He can be introduced into material by both neutron irradiation and tritium radioactive decay. Presence of He in plasma-facing materials may significantly influence their mechanical properties and surface morphology [1, 2], as well as hydrogen isotope recycling [3, 4]. Tungsten (W) will be used as a plasma-facing material in ITER divertor [5], and it is considered also for application in future fusion devices. Therefore, investigation of He interaction with W is of great interest.
- ПубликацияОткрытый доступHYDROGEN CO-DEPOSITION WITH METALS IN PLASMA DISCHARGE(НИЯУ МИФИ, 2017) Krat, S. A.; Gasparyan, Yu. M.; Vasina, Ya. A.; Pisarev, A. A.; Писарев, Александр Александрович; Крат, Степан Андреевич; Гаспарян, Юрий МикаэловичDeposition of a single element film is always accompanied by co-deposition of a certain amount of other elements. This can be done properly to improve properties of the coating or due to contamination by impurities. In the field of thermonuclear fusion research, where hydrogen isotopes are used as a fuel, co-deposition with sputtered material from the wall is one of major mechanisms of hydrogen isotopes accumulation in the installation. Since D-T fuel will be used in ITER and future fusion reactors, accumulation of radioactive tritium will limit the lifespan of the installations due to safety concerns. For example, tritium accumulation in ITER is limited by 1 kg. This is why carbon materials were not accepted for the use in ITER. Basing on experiments, it was predicted that the safety limit could be reached after 100 of shots with tritium. Recent experiments in JET [1] demonstrated in the case of “ITER-like” wall (first wall – Be, divertor area - tungsten) accumulation of deuterium fuel in the co-deposits was 20 times lower than in the full-carbon wall campaign. This is both due to smaller amount of co-deposits and smaller concentration of deuterium in them.
- ПубликацияОткрытый доступDEUTERIUM RE-EMISSION AND THERMAL DESORPTION FROM IRON AND EUROFER(НИЯУ МИФИ, 2017) Ryabtsev, S. A.; Gasparyan, Yu. M.; Ogorodnikova, O. V.; Harutyunyan, Z. R.; Pisarev, A. A.; Арутюнян, Зорий Робертович; Огородникова, Ольга Вячеславовна; Писарев, Александр Александрович; Гаспарян, Юрий МикаэловичReduced-activation ferritic-marthensitic (RAFM) steels, such as Eurofer, are considered as candidates for structural materials in fusion reactors due to the high thermal conductivity, the low thermal expansion coefficient and good resistance to radiation swelling. There are also some concepts of fusion reactors, where RAFM steels also considered as material for plasma-facing components. In this regard, the key aspects of hydrogen (H) isotopes interaction with RAFM steels, such as tritium (T) retention and migration in these materials are particularly important as a point of safety concern.
- ПубликацияТолько метаданныеThe dependence of lithium emissivity from temperature in vacuum ЗАВИСИМОСТЬ СТЕПЕНИ ЧЕРНОТЫ ЛИТИЯ ОТ ТЕМПЕРАТУРЫ В ВАКУУМЕ(2019) Prishvitsyn, A. S.; Krat, S.; Harina, A. P.; Pisarev, A. A.; Пришвицын, Александр Сергеевич; Крат, Степан Андреевич; Писарев, Александр Александрович© 2019 National Research Center Kurchatov Institute. All rights reserved.Correct interpretation of IR video observation data of the surfaces of plasma-facing elements in fusion devices requires detailed knowledge about the emissivity factor of these surfaces in different conditions. In this work, results of emissivity measurements for free metallic lithium surface and a lithium surface supported by the capillary-porous system (CPS) are measured as a function of temperature in the range from 400 to 800 K. Emissivity of solid lithium changed from ~0.04 at 400 K to ~0.09 at 453 K. During melting a sudden drop of emissivity down to ~0.04 was observed. Emissivity increased linearly from 0.04 to ~0.15 with temperature increasing from 455 to 800 K. For fully wetted CPS, emissivity was close to that of free lithium surface for temperature up to ~570 K, while at higher temperature it was lower, probably due to changes in microrelief at high temperatures.