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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- ПубликацияОткрытый доступPRODUCTION AND RECOVERY OF RADIATION-INDUCED DE-FECTS IN TUNGSTEN(НИЯУ МИФИ, 2014) OGORODNIKOVA, O. V.; SUGIYAMA, K.; CIUPIŃSKI, Ł.; GRZONKA, J.; GASPARYAN, Yu.; EFIMOV, V.; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна; Ефимов, Виталий СергеевичAccumulation and recovery of radiation defects under/after self-ion irradia-tion in tungsten (W) have been investigated via decoration with deuterium (D) and scanning transmission electron microscopy. The deuterium was incorpo-rated in damaged material by low-energy D plasma. The D retention at radia-tion-induced defects in each sample was subsequently measured by nuclear reaction analysis allowing determination of the D concentration at depths up to 6 μm. The total D retention was measured by thermal desorption spectroscopy. It was shown that pre-irradiation with self-ions led to rather high D retention (≥ 0.1 at.%) in W even at high temperatures (≥ 700 K) due to formation of defects with high de-trapping energy for deuterium. The annealing of defects with low trapping energy for D occurs intensively in the temperature range between 300 and 700 K. The radiation-induced defects with high de-trapping energy for D are thermally stable at least up to 1100 K. Moreover, the clear evidence of an increase of the D retention at radiation-induced defects in polycrystalline W at annealing temperature of around 1000 K was found. This observation suggested that 1000 K can be maximum temperature of agglomeration of vacancy clusters in nano- or micro-voids. This conclusion was supported by scanning transmis-sion electron microscopy data which showed a coalescence of small clusters in big ones after annealing. The increase of the D retention at annealing tempera-ture of ~1000 K was not observed for recrystallized W. The mechanism of re-covery of radiation-induced defects depending on the grain size and impurities is discussed.
- ПубликацияТолько метаданныеEffect of the presence of helium in tungsten on deuterium retention(2021) Kanashenko, S.; Ogorodnikova, O. V.; Harutyunyan, Z. R.; Gasparyan, Y. M.; Efimov, V. S.; Kharkov, M. M.; Kaziev, A. V.; Огородникова, Ольга Вячеславовна; Арутюнян, Зорий Робертович; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Харьков, Максим Михайлович; Казиев, Андрей Викторович© 2021Tungsten (W) samples were pre-irradiated with low-energy helium (He) ions with an energy of 80 eV, flux of 1021 He/m2s, at a sample temperature of 1200–1250 K in a inductively coupled plasma (ICP) source facility. Such irradiation conditions led to a formation of a nano-structured surface layer of tungsten, called ‘fuzz’. These samples were then irradiated with D3+ ions with an energy of 2 keV and small doses of 1019 D/m2 at room temperature and in-situ thermal desorption analysis (TDS) was performed. It was found that the main factor determining the deuterium (D) retention in W samples pre-irradiated with helium is the concentration of helium below the surface, namely, the D retention was increased with decreasing the He concentration until the nanostructured W ‘fuzz’ was removed. The effect of nano-structured tungsten ‘fuzz’ is only in a decrease of the reflection coefficient of deuterium ions compared to a smoother surface, resulting in the increase of the D influx into W and, consequently, increase of the D retention. However, this increase has a minor effect on the D retention compared to the He concentration in the subsurface layer of W.
- 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 метаданныеRelease of ion-implanted 3He and D from tungsten under subsequent 4He ion irradiation(2025) Umerenkova, A.; Harutyunyan, Z.; Ogorodnikova, O.; Gasparyan, Y.; Ostojic, N.; Efimov, V.; Умеренкова, Анастасия Сергеевна; Арутюнян, Зорий Робертович; Огородникова, Ольга Вячеславовна; Гаспарян, Юрий Микаэлович; Остойич, Никола; Ефимов, Виталий Сергеевич
- ПубликацияОткрытый доступВЛИЯНИЕ ВЫСОКОТЕМПЕРАТУРНОГО ОТЖИГА НА МИКРОСТРУКТУРУ СПЛАВА W–Cr–Y(НИЯУ МИФИ, 2025) Никитин, А. А.; Рогожкин, С. В.; Огородникова, О. В.; Лямкин, П. В.; Никитин, Александр Александрович; Огородникова, Ольга Вячеславовна; Рогожкин, Сергей ВасильевичВ работе методами атомно-зондовой томографии и просвечивающей электронной микроскопии проведен анализ изменений микроструктуры, размеров зерен и локального химического состава сплава W–Cr–Y в результате вакуумного отжига при температурах 1000 и 1200°C. В исходном состоянии сплав характеризуется зернами со средним размером ~1 мкм, по границам которых располагаются частицы, обогащенные иттрием и кислородом с размерами от 10 до 180 нм. Отжиг приводит к рекристаллизации материала с уменьшением среднего размера зерен до 100 нм при температуре 1000°C и до 270 нм при температуре 1200°C. Дополнительно наблюдается растворение оксидов иттрия и формирование новых наноразмерных кластеров во внутризеренной области, состав и объемная плотность которых, зависят от условий отжига.
- ПубликацияТолько метаданныеDeuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions(2021) Kanashenko, S.; Harutyunyan, Z.; Gasparyan, Y.; Ryabtsev, S.; Efimov, V.; Ogorodnikova, O.; Pisarev, A.; Арутюнян, Зорий Робертович; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич; Огородникова, Ольга Вячеславовна; Писарев, Александр Александрович© 2021The effect of He-induced defects in tungsten on the efficiency of trapping of deuterium ions in the subsurface layer was studied using thermal desorption spectroscopy (TDS). The W sample was pre-irradiated with 3 keV helium ions at room temperature and various fluences in the range of 1019 – 5 × 1021 He/m2. Then, it was exposed to a probe fluence of 1019 D/m2 of 2 keV D3+ (670 eV/D) ions, and in-situ TDS was performed. The de-trapping energy for D atoms increased with the increase of the He pre-irradiation fluence. On the other hand, a strong decrease in the D retention was observed if the He fluence increased above 1021 He/m2. At the highest He fluence of 5 × 1021 He/m2 deuterium trapping was possible only after partial release of He atoms. By comparison of experimental TDS spectra with modeling, the de-trapping energies of D atoms from various defects were estimated.
- ПубликацияТолько метаданныеMAGNETRON SPUTTER DEPOSITION OF TUNGSTEN COATINGS IN DEUTERIUM–HELIUM MIXTURES(2023) Kharkov, M.; Lomonosov, G. S.; Kolodko, D. V.; Kukushkina, M. S.; Kaziev, A. V.; Tumarkin, A. V.; Ogorodnikova, O. V.; Харьков, Максим Михайлович; Ломоносов, Глеб Сергеевич; Колодко, Добрыня Вячеславич; Кукушкина, Маргарита Сергеевна; Казиев, Андрей Викторович; Тумаркин, Александр Владимирович; Огородникова, Ольга Вячеславовна
- 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 доступPENETRATION, DIFFUSION AND TRAPPING OF DEUTERIUM IN TUNGSTEN UNDER EXPOSURE TO THERMAL ATOMIC BEAM(НИЯУ МИФИ, 2016) OGORODNIKOVA, O. V.; VON TOUSSAINT, U.; MARKELJ, S.; Огородникова, Ольга ВячеславовнаThe present work focuses on a number of compelling fundamental science problems relevant to plasma-material interactions. Several theoretical approaches were used. Molecular dynamic (MD) model and binary collision code TRIM were used to define the reflection coefficient and penetration depth of atomic and low-energy deuterium in tungsten. Rate equation theory and analytical model were used for the description of the deuterium penetration, diffusion and trapping in tungsten. An analytical expression for the rate of migration and trapping of hydrogen isotopes in a metal was derived. Using this expression, experimentally observed dependences of accumulation of the atomic and low-energy deuterium in tungsten on the incident energy, ion flux and temperature were explained. The calculations of the deuterium diffusion with trapping at radiation-induced defects in tungsten by analytical model are consistent with numerical calculations using rate-equation model. MD calculations show an agreement with a binary collision code TRIM only in a very narrow range of deuterium energies between 1 and 20 eV. Incorporation of the data of reflection and penetration of deuterium in the macroscopic modelling has been done to verify the range of validity of calculations using molecular dynamic MD and binary collision code TRIM by comparison of modelling results with experimental data. Modelling results are consistent with experiments using reflection and penetration data obtained from TRIM code for deuterium incident energy above 1 eV. Otherwise, the parameters obtained from MD should be incorporated in the rate-equation model to have a good agreement with the experiments. The present model allows us to understand interaction of thermal atomic deuterium beam with tungsten and validate reflection coefficient and mean projective range obtained by TRIM and MD calculations against experiments.
- ПубликацияТолько метаданныеHelium and deuterium retention in Eurofer97 under sequential irradiation at low fluxes(2022) Ogorodnikova, O. V.; Harutyunyan, Z.; Gasparyan, Y.; Efimov, V.; Огородникова, Ольга Вячеславовна; Арутюнян, Зорий Робертович; Гаспарян, Юрий Микаэлович; Ефимов, Виталий Сергеевич© 2022The helium (He) retention and the influence of He-induced defects on the deuterium (D) retention and migration in Eurofer97 were investigated by in-situ and ex-situ thermal desorption spectroscopy technique. Samples were pre-irradiated with 3 keV He ions in the fluence range of 1019–1022 He/m2, then irradiation with 2 keV D3+ ions (667 eV/D) with a fluence of 1021 D/m2 was performed. Experiments were carried out at the sample temperature of 300 K. It was shown that the D retention in Eurofer97 increases and decreases with pre-irradiation with He fluences below and above 1021 He/m2, respectively. However, in all cases of He pre-irradiation, the D retention is higher than that in Eurofer97 without He pre-irradiation. The effect of the reduction of the D retention at He fluences above 1021 He/m2 can be connected with either the formation of open porosity due to interconnected bubbles or the strain field induced by high pressurized He bubbles that preventing D penetration into the bulk of a metal. Both effects reduce the D diffusion towards the bulk of a metal and, therefore, lead to a decrease in the D retention. Our data of in-situ and ex-situ experiments revealed that HemVn complexes in the temperature range of 600–800 K are unstable and transformed in stable HemVn complexes in the temperature range of 900–1100 K after air exposure. Due to a formation of oxide layer during a contact with the atmosphere, ex-situ TDS of D leads to a shift of the D release temperature in the high-temperature range compared to in-situ TDS in both cases with and without He pre-irradiation. Finally, the presence of He in a metal lattice will have the dominant influence on the D retention in the future fusion devices together with neutron irradiation and high temperature gradient. In the case of He saturation, the similar D retention was measured in different bcc metals and their alloys.