Персона: Огородникова, Ольга Вячеславовна
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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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Ольга Вячеславовна
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- 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.
- ПубликацияТолько метаданныеTungsten fuzz annealing effect on deuterium retention in polycrystalline tungsten(2022) Kanashenko, S.; Harutyunyan, Z.; Ogorodnikova, O. V.; Gasparyan, Y.; Efimov, V.; Sorokin, I.; Sergeev, N.; Арутюнян, Зорий Робертович; Огородникова, Ольга Вячеславовна; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Сорокин, Иван Александрович; Сергеев, Никита Сергеевич© 2022 Elsevier B.V.Using a beam-plasma discharge device operating on helium (He), tungsten with the fuzz on the surface (Wf) has been formed by irradiating polycrystalline tungsten (W) samples with He ions with an energy of ∼150 eV and the fluence of ∼6 × 1024 He/m2 at the temperature of 1273 K. The deuterium (D) retention in Wf annealed at different temperatures was studied by thermal desorption spectroscopy (TDS). Before and after annealing at temperatures of 1000,1200,1400 and 1600 K, Wf was irradiated at room temperature by 2 keV D3+(667 eV/D) ions with the fluence of 1021 D/m2, then in-situ TDS was performed after each irradiation. Annealing W above 1200 K clearly changes the retention mechanism of D: the TDS spectrum consisting of multiple peaks changes to an almost single-peak spectrum. Annealing at 1600 K leads to surface smoothing and the decrease of the D retention by a factor of two compared to the annealing at 1000 K. This can be explained by an increase of the reflection coefficient for the flat W surface. However, the D retention in Wf is significantly higher compared to that in W without He plasma exposure even after annealing at 1600 K, because there are still He bubbles in Wf that effectively trap D
- ПубликацияТолько метаданныеAnnealing effect on deuterium retention in W-Cr-Y alloy(2024) Wang, Y.; Harutyunyan, Z.; Gasparyan, Y.; Ogorodnikova, O.; Sinelnikov, D.; Efimov, N.; Umerenkova, A.; Grishaev, M.; Арутюнян, Зорий Робертович; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна; Синельников, Дмитрий Николаевич; Ефимов, Никита Евгеньевич; Умеренкова, Анастасия Сергеевна; Гришаев, Максим Валерьевич
- ПубликацияОткрытый доступPositron annihilation spectroscopy study of radiation-induced defects in W and Fe irradiated with neutrons with different spectra(2020) Majerle, M.; Cizek, J.; Simakov, S.; Gann, V. V.; Ogorodnikova, O. V.; Огородникова, Ольга Вячеславовна© 2020, The Author(s).The paper presents new knowledge on primary defect formation in tungsten (W) and iron (Fe) irradiated by fission and high-energy neutrons at near-room temperature. Using a well-established method of positron-annihilation lifetime-spectroscopy (PALS), it was found that irradiation of W in the fission reactor and by high-energy neutrons from the p(35 MeV)-Be generator leads to the formation of small radiation-induced vacancy clusters with comparable mean size. In the case of Fe, smaller mean size of primary radiation-induced vacancy clusters was measured after irradiation with fission neutrons compared to irradiation with high-energy neutrons from the p(35 MeV)-Be generator. It was found that one of the reasons of the formation of the larger size of the defects with lower density in Fe is lower flux in the case of irradiation with high-energy neutrons from the p(35 MeV)-Be source. The second reason is enhanced defect agglomeration and recombination within the energetic displacement cascade at high energy primary knock-on-atoms (PKAs). This is consistent with the concept of the athermal recombination corrected (arc-dpa) model, although the measured dpa cross-section of both fission neutrons and wide-spectrum high-energy neutrons in W is between the conventional Norgett–Robinson–Torrens (NRT-dpa) and arc-dpa predictions. This means that the physics of the primary radiation effects in materials is still not fully known and requires further study through a combination of modeling and experimental efforts. The present data serve as a basis for the development of an improved concept of the displacement process.
- ПубликацияОткрытый доступHYDROGEN AND HELIUM RETENTION IN TUNGSTEN UNDER ION IRRADIATION(НИЯУ МИФИ, 2017) Gasparyan, Yu.; Zibrov, M.; Efimov, V.; Ryabtsev, S.; Ogorodnikova, O.; Pisarev, A.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович; Огородникова, Ольга ВячеславовнаInteraction of helium and hydrogen ions with tungsten is intensively investigated during last decades in relation to construction of fusion reactor. Tungsten has the high melting temperature and the energy threshold for sputtering and, therefore, is considered as plasma facing material (PFM) in fusion devices in the area of largest heat loads and small energies of ions (divertor area). In particular, tungsten will be used in the international experimental reactor ITER, which is now under construction.
- ПубликацияОткрытый доступPERSPECTIVE FUNCTIONAL MATERIALS UNDER EXTREME CONDITIONS: HIGH HEAT AND PARTICLE FLUXES AND NEUTRON IRRADIATION(НИЯУ МИФИ, 2019) OGORODNIKOVA, O. V.; KLIMOV, N. S.; GASPARYAN, Yu. M.; EFIMOV, V. S.; POSKAKALOV, А. G.; KAZIEV, A. V.; KHARKOV, M. M.; VOLKOV, N. V.; Казиев, Андрей Викторович; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна; Ефимов, Виталий Сергеевич; Харьков, Максим МихайловичIn a thermonuclear reactor, materials will be irradiated with energetic particles of hydrogen isotopes and helium (He), neutrons, and heat fluxes. Tungsten and dense nano-structured tungsten (W) coatings are used as plasma-facing materials in current tokamaks and are the reference materials of the ITER divertor and DEMO reactor and the possibility of using reduced-activated ferrite-martensitic, RAFM, steels not only as structural materials, but also as the material of the first wall of the thermonuclear reactor is considered. Also, these steels, together with a new generation oxide dispersion strengthening (ODS) steels by the addition of Y2O3 particles are considered as promising materials for fast neutron fuel cladding. In structural materials of the reactor core on fast neutrons at deep burn-up of nuclear fuel (15-20% and more t.a.) and, especially, the first wall and other nodes of the fusion reactor chamber, together with a high level of radiation damage, there will be an accumulation of significant amounts of helium and hydrogen isotopes. Hydrogen embrittlement and helium swelling in a fusion reactor are important issues that determine the applicability of the material and can cause a reduction in the lifetime of reactor components. Moreover, accumulation of helium in a metal at elevated temperatures leads to the growth of the so-called nano-structured ‘fuzz’ on the metal surface as well as high heat fluxes significantly change the near surface layers by melting and cracking. In this regard, the study of the accumulation of helium and hydrogen isotopes in W-based materials and in RAFM steels, the study of surface modification under the influence of plasma irradiation and a fundamental understanding of radiation damage in W- and Fe- based materials is critical for the design of materials in extreme environment, for example, for fusion reactors.
- ПубликацияОткрытый доступDEUTERIUM RETENTION IN DENSE AND DISORDERED NANOSTRUCTURED TUNGSTEN COATINGS(НИЯУ МИФИ, 2017) OGORODNIKOVA, O. V.; RUSET, C.; DELLASEGA, D.; PEZZOLI, А.; PASSONI, M.; SUGIYAMA, К.; GASPARYAN, YU.; EFIMOV, V.; BALDEN, M.; MATERN, G.; KOCH, F.; Огородникова, Ольга Вячеславовна; Ефимов, Виталий Сергеевич; Гаспарян, Юрий МикаэловичThree types of nano-structured tungsten (W) coatings were investigated in respect to deuterium (D) retention after the low-energy D plasma exposure. The D depth profile was measured up to 6 μm by nuclear reaction analysis (NRA) and the total deuterium retention was measured by thermal desorption spectros-copy (TDS). In the present work, we investigated (i) a dependence of the D retention in a W coating on substrate, (ii) a dependence of the D retention in a W coating on the nano-crystalline structure, namely, columnar-like or amor-phous-like, and (iii) the D retention at an interface between layers. It was shown that most of deuterium is trapped in the interlayer between W coating and substrate. Consequently, the D retention in the interlayer between different materials can be a concern. It was found that all types of coatings show higher D accumulation compared to bulk polycrystalline W. The disodered W coating produced by Pulsed Laser Deposition (PLD) has highest deuterium (D) concen-tration compared to dense W coating produced by Combined Magnetron Sput-tering and Ion Implantation (CMSII) technology and W coating produced by standard vacuum magnetron-sputtering (SMS) method. The lowest D concen-tration was found in SMS-W coating. No significant influence of the substrate on the D retention in coatings was found. The D retention correlates with mi-crostructure of multilayer W coating: the D retention drastically increases with decreasing the grain size. Consequently, from point of view of the hydrogen isotope retention, coarse-grained crystals are recommended for application of W-based materials in fusion devices. At the same time, coarse-grained crystals are undesirable from point of view of blister formation under the plasma expo-sure. Nano-crystalline structure of W coatings suppresses the blister formation. A compromise in the development of new promising nanostructured tungsten films is necessary to keep the hydrogen concentration at an acceptable level and reducing/preventing high density of defects at the interface between nanostruc-tured coating and substrate.
- ПубликацияОткрытый доступВЛИЯНИЕ ЭНЕРГИИ ИОНОВ НА ЗАМЕЩЕНИЕ ИЗОТОПОВ ГЕЛИЯ В ВОЛЬФРАМЕ(НИЯУ МИФИ, 2024) УМЕРЕНКОВА, А. С.; АРУТЮНЯН, З. Р.; ГАСПАРЯН, Ю. М.; ЕФИМОВ, В. С.; ОГОРОДНИКОВА, О. В.; ОСТОЙИЧ, Н.; Остойич, Никола; Арутюнян, Зорий Робертович; Умеренкова, Анастасия Сергеевна; Огородникова, Ольга Вячеславовна; Гаспарян, Юрий Микаэлович; Ефимов, Виталий СергеевичВ будущих термоядерных реакторах изменение структуры материалов обращенных к плазме элементов (ОПЭ) реактора и накопление гелия как продукта термоядерной реакции в них будет влиять на эффективность захвата и рециклинг изотопов водорода. Вольфрам широко используется в современных термоядерных установках в качестве материала облицовки ОПЭ, поэтому поведения гелия в этом материале вызывает интерес.
- ПубликацияТолько метаданныеAnnealing of radiation-induced defects in tungsten: Positron annihilation spectroscopy study(2019) Terentyev, D.; Funtikov, Y. V.; Stolbunov, V. S.; Ogorodnikova, O. V.; Dubov, L. Y.; Stepanov, S. V.; Shtotsky, Y. V.; Efimov, V.; Gutorov, K.; Огородникова, Ольга Вячеславовна; Дубов, Леонид Юрьевич; Степанов, Сергей Всеволодович; Штоцкий, Юрий Владимирович; Ефимов, Виталий Сергеевич; Гуторов, Константин Михайлович© 2019 Elsevier B.V. Positron annihilation lifetime spectroscopy (PALS) was applied to study the annealing of radiation-induced defects in polycrystalline tungsten (W) irradiated with 21.6 MeV protons at 100 °C up to a fluence of 5 × 10 15 p/cm 2 . Three components were observed in the measured spectra: short-lifetime of 100–120 ps (positron annihilation in the defect-free W lattice), medium-lifetime of ∼190–330 ps (annihilation at mono-vacancies and small vacancy cluster containing ∼ 2–4 vacancies) and long-lifetime of ∼500 ps (annihilation in large vacancy clusters containing more than 10 vacancies). The irradiation of W with protons at 100 °C, primary, led to the formation of mono-vacancies, self-interstitial defects were created as well but migrated towards sinks during the irradiation. Onset of vacancy diffusion in W starts already at 200 °C before defect recovery stage III. After annealing at ∼400 °C, a sharp drop in the intensity of the positron medium-life component together with a simultaneous increase in positron lifetime from ∼220 to ∼280 ps is observed, and a long-life component appears. This indicates migration and annealing of vacancies and their agglomeration in large vacancy clusters. After annealing at 500–700C, the intensity of long-life component increases indicating the growth of large vacancy clusters but at 900 °C they anneal completely as the mean lifetime recovers nearly to the value measured in the un-irradiated material.
- ПубликацияТолько метаданныеDeuterium Retention in a Nanostructured Tungsten Surface Layer Formed during High-Temperature Irradiation with Helium Plasma(2020) Harutyunyan, Z. R.; Ogorodnikova, O. V.; Aksenova, A. S.; Gasparyan, Y. M.; Efimov, V. S.; Kharkov, M. M.; Kaziev, A. V.; Volkov, N. V.; Арутюнян, Зорий Робертович; Огородникова, Ольга Вячеславовна; Аксенова, Александра Сергеевна; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Харьков, Максим Михайлович; Казиев, Андрей ВикторовичThe preliminary irradiation of a tungsten sample with low-energy helium ions (80 eV, flux of 10(21) m(-2) s(-1)) at a temperature of 1200-1250 K in a facility with an inductive RF discharge leads to the formation of a nanostructured tungsten surface layer, which is referred to as fuzz. After that, the sample is subjected to a set of annealing procedures and irradiations with ions with an energy of 2 keV (0.67 keV per D) at low fluences of 10(19)-10(20) m(-2). Deuterium retention at each stage is analyzed by in-situ thermal desorption spectroscopy. An increase in the helium concentration in the sample leads to a significant change of deuterium retention. At high helium concentrations, deuterium retention becomes low. Annealing in the temperature range of 1000-1400 K leads to helium desorption, modification of the surface layer and defects, and, as a consequence, an increase in the amplitude of the main deuterium desorption peak and a shift of the peak to higher temperatures. Annealing at a temperature of 1600 K leads to removal of the nanostructured fuzz from the tungsten surface and a decrease in the deuterium retention on account of an increase in the reflection coefficient from a smoother surface.