Персона: Гаспарян, Юрий Микаэлович
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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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Руководитель научной группы "Плазменные и лазерные технологии новых материалов для ядерной и термоядерной энергетики"
Руководитель научной группы -Международный центр ядерных компетенций (МЦЯДКОМ)
Руководитель научной группы -Международный центр ядерных компетенций (МЦЯДКОМ)
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Юрий Микаэлович
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- ПубликацияТолько метаданныеDeuterium and helium retention in W with and without He-induced W ‘fuzz’ exposed to pulsed high-temperature deuterium plasma(2019) Tokitani, M.; Ogorodnikova, O. V.; Klimov, K. S.; Poskakalov, A. G.; Kaziev, A. V.; Kharkov, M. M.; Efimov, V. S.; Gasparyan, Y. M.; Volkov, N. V.; Alimov, V. K.; Огородникова, Ольга Вячеславовна; Климов, Николай Сергеевич; Казиев, Андрей Викторович; Харьков, Максим Михайлович; Ефимов, Виталий Сергеевич; Гаспарян, Юрий Микаэлович© 2018 Elsevier B.V. In the present work, helium (He) was incorporated into tungsten (W) samples by inductively coupled plasma (ICP) source above the threshold of He-induced W ‘fuzz’ formation on W surface. Then, W samples with and without nano-structured W ‘fuzz’ were exposed to pulsed heat loads using deuterium (D) plasma in quasi-stationary high-current plasma gun QSPA-T. The pulse duration was 1 ms and number of pulses was varied from one to thirty to simulate ITER transient events with surface heat load parameters relevant to edge-localized-mode (ELM) impacts. The irradiation was performed below and above the W melting threshold. The D and He retention in each irradiated sample was measured by a method of thermal desorption spectroscopy. We examined the impact of (i) ELMs-like events and (ii) formation of He-induced nano-structured ‘fuzz’ on the D retention in W. We found that the D retention was the highest for samples irradiated by plasma gun above the melting threshold after thirty pulses. Moreover, the D retention after 10 pulses of deuterium plasma gun exposure was higher than that after stationary low-energy plasma exposure at sample temperature of either 600 or 700 K indicating the dominate influence of ELM's-like events on the D retention compared to normal operation regime. The D retention in W samples with the presence of He-induced W ‘fuzz’ was slightly smaller than without that after one pulse of plasma gun exposure with heat load below the W melting temperature. The W ‘fuzz’ was not disappear in this loading conditions, only the length and thickness of nano-structured W fibres were reduced by factors of ∼4 and ∼2, respectively. The He concentration in W with W ‘fuzz’ was decreased by a factor of about 3 after one pulse of plasma gun exposure. The results obtained give possibility to assess the particle retention in divertor areas subjected to high thermal loads at different operation regimes.
- ПубликацияОткрытый доступЗАМЕЩЕНИЕ ИЗОТОПОВ ГЕЛИЯ В ВОЛЬФРАМЕ ПРИ ПОСЛЕДОВАТЕЛЬНОМ ИОННОМ ОБЛУЧЕНИИ(НИЯУ МИФИ, 2023) Умеренкова, А. С.; Гаспарян, Ю. М.; Арутюнян, З. Р.; Ефимов, В. С.; Сергеев, Н. С.; Сорокин, И. А.; Остойич, Н.; Остойич, Никола; Гаспарян, Юрий Микаэлович; Умеренкова, Анастасия Сергеевна; Ефимов, Виталий Сергеевич; Сорокин, Иван Александрович; Арутюнян, Зорий Робертович; Сергеев, Никита СергеевичHelium isotope exchange in tungsten during sequential irradiation by 3He and 4He ions at room temperature was investigated. Tungsten samples were irradiated in two ways: by 3 keV mass-separated ion beams, or by low energy ions in plasma discharge. The He amount in W after irradiation was measured using ex-situ (up to 2500 K) thermal desorption spectroscopy. Despite the very high binding energy of He with lattice defects in W, a very high efficiency of He isotope exchange was observed.
- 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 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.
- ПубликацияТолько метаданныеSurface Structure Modification and Deuterium Retention in Tungsten under Pulsed Plasma Loads(2019) Poskakalov, A. G.; Klimov, N. S.; Gasparyan, Y. M.; Ogorodnikova, O. V.; Efimov, V. S.; Климов, Николай Сергеевич; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна; Ефимов, Виталий Сергеевич© 2019, Pleiades Publishing, Ltd.Modification of the surface layer and deuterium accumulation in tungsten targets under plasma irradiation in a quasi-stationary plasma accelerator with an intrinsic magnetic field QSPA-T, which reproduces the conditions (plasma thermal load of 0.2-5 MJ/m2, pulse duration of 0.1-1.2 ms) typical of ELM events in ITER, are studied. Using a scanning electron microscope, structure modifications at the surface and in the bulk after deuterium plasma irradiation are analyzed. The observed changes in the near-surface layer are compared with the calculated data on the change in the internal structure of tungsten under intense thermal action obtained as a result of the numerical solution of the heat conduction problem. The total deuterium retention in the samples was measured using thermal desorption spectroscopy, and it was in the range of (3-4) × 1016 particles/cm2 for the samples melted during plasma exposure. These numbers exceed by an order of magnitude the values obtained for samples without traces of melting.
- ПубликацияТолько метаданныеHelium retention in tungsten irradiated with He+ ion beam at elevated temperatures(2019) Kanashenko, S.; Ivanov, Y.; Ryabtsev, S.; Gasparyan, Y.; Efimov, V.; Harutyunyan, Z.; Aksenova, A.; Poskakalov, A.; Pisarev, A.; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Арутюнян, Зорий Робертович; Аксенова, Александра Сергеевна; Писарев, Александр Александрович© 2019Helium (He) retention in re-crystallized tungsten (W) irradiated with He+ ions at elevated temperatures (700–1200 K) and fluences in the range of 1020–1022 He/m2 was investigated by means of thermal desorption spectroscopy (TDS). Corresponding surface modifications were analyzed by scanning electron microscopy. Blisters were observed after irradiation at 700 and 1000 K, while the increase of the irradiation temperature up to 1200 K led to development of a complex sponge-like structure on the W surface. Significant surface transformations correlated with appearance of low temperature peaks in TDS spectra below the irradiation temperature. Possible mechanisms and explanations are discussed.
- ПубликацияТолько метаданныеInfluence of plasma heat loads relevant to ITER transient events on deuterium retention in tungsten(2020) Poskakalov, A. G.; Gasparyan, Y. M.; Efimov, V. S.; Kovalenko, D. V.; Klimov, N. S.; Ogorodnikova, O. V.; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Климов, Николай Сергеевич; Огородникова, Ольга ВячеславовнаDeuterium (D) retention in Tungsten (W) under plasma heat loads relevant to edge localized modes in ITER was experimentally investigated at the QSPA-T plasma gun facility. Samples were exposed to 1.0 ms D plasma pulses with different heat loads in the range of 0.4-3.7 MJm(-2) (heat flux factor P root t = 13.3-123 MJm(-2)s(-0.5)). A significant D retention was observed already after one pulse. Moreover, the D retention grew up continuously with increasing the power load, although the surface was melted at highest loads (above 1.4 MJ m(-2)). The D retention was higher than that in the case of stationary plasma irradiation at 600-700 K, indicating possible significant contribution of ELM's-like events to the total D retention. All stages of the experiments (irradiation, storage time and TDS) have been simulated using the TMAP 7 code.
- ПубликацияТолько метаданныеRetention of Deuterium in the Surface Layers of Tungsten Preliminarily Irradiated with Helium Ions(2020) Harutyunyan, Z. R.; Gasparyan, Y. M.; Efimov, V. S.; Ryabtsev, S. A.; Pisarev, A. A.; Арутюнян, Зорий Робертович; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Писарев, Александр Александрович© 2020, Allerton Press, Inc.Abstract: The retention of deuterium in tungsten preliminarily irradiated with helium ions is investigated by means of thermal desorption spectroscopy (TDS). Preliminary irradiation is performed with a He+ ion beam having an energy of 3 keV and fluence ranging in the interval 1019–1021 He m−2, in order to produce a defect structure typical of different degrees of damage. The specimens are then irradiated with D+3 ions having an energy of 2 keV and a weak fluence of 1019 D m−2, with subsequent TDS analysis to characterize the interaction between deuterium and helium-induced defects. It is shown that an increase in the deuterium retention is observed as soon as irradiation with the minimal fluence of helium ions, but it falls to the background level at fluences above 5 × 1021 He m−2.
- ПубликацияОткрытый доступCORRELATION OF DEUTERIUM RETENTION WITH CRYSTALLINE STRUCTURE IN DENSE AND DISORDERED TUNGSTEN COATINGS(НИЯУ МИФИ, 2017) Ogorodnikova, O. V.; Ruset, C.; Dellasega, D.; Pezzoli, A.; Passoni, M.; Sugiyama, K.; Gasparyan, Yu.; Efimov, V.; Ефимов, Виталий Сергеевич; Гаспарян, Юрий Микаэлович; Огородникова, Ольга ВячеславовнаDense nano-structured tungsten (W) coatings are used as plasma-facing materials in current tokamaks and thick coatings are suggested to be used also for the future fusion devices, ITER and DEMO. In this study, deuterium (D) retention in various W coatings was investigated to understand dependences of the D retention on the crystalline structure of each W coating and on the substrate material.
- ПубликацияТолько метаданныеHelium retention in tungsten under plasma and ion beam irradiation and its impact on surface morphology(2020) Gasparyan, Y.; Ryabtsev, S.; Efimov, V.; Harutyunyan, Z.; Aksenova, A.; Poskakalov, A.; Kaziev, A.; Kharkov, M.; Ogorodnikova, O.; Pisarev, A.; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Арутюнян, Зорий Робертович; Аксенова, Александра Сергеевна; Казиев, Андрей Викторович; Харьков, Максим Михайлович; Огородникова, Ольга Вячеславовна; Писарев, Александр АлександровичHelium (He) is a product of deuterium-tritium (DT)-fusion reaction and will be a natural impurity in DT plasma in future fusion devices. He retention in tungsten irradiated by plasma and mass-separated ions in a wide temperature range (300-1200 K) was investigated by means of thermal desorption spectroscopy (TDS). He retention did not exceed the level of 1.5 x 10(21) He m(-2) for all investigated samples. A significant effect of air exposure on TDS spectra was demonstrated. In contrast to in situ TDS measurements, He release after interaction with the air started from similar to 400 K, even in the case of high temperature irradiation. Changes in surface morphology were analyzed by secondary electron microscopy. Blisters were found at the surface after ion irradiation at low temperatures. Acceleration of surface modification and more complex surface morphology was observed in the case of irradiation at temperatures above 1000 K.