Персона:
Огородникова, Ольга Вячеславовна

Организационные подразделения

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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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Огородникова

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Ольга Вячеславовна

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Deuterium 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.
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МОДЕЛИРОВАНИЕ РАДИАЦИОННЫХ ПОВРЕЖДЕНИЙ В СПЛАВАХ ВОЛЬФРАМА С ИСПОЛЬЗОВАНИЕМ ИОННОГО ОБЛУЧЕНИЯ
(НИЯУ МИФИ, 2023) Никитин, А. А.; Рогожкин, С. В.; Бобырь, Н. П.; Федин, П. А.; Огородникова, О. В.; Рогожкин, Сергей Васильевич; Огородникова, Ольга Вячеславовна; Никитин, Александр Александрович
In this work, a comprehensive study of a W-6Re and W-10Cr alloys after accelerated irradiation with ions to a damage dose of 10 displacements per atom at temperatures of 300 and 500 °C was carried out. A detailed chemical analysis of radiation induced defects acquired by means of transmission electron microscopy and atom probe tomography. It is shown that, as a result of irradiation, nanosclae clusters enriched in rhenium and chromium are formed. In addition, a high density (of the order of 1024 m-3) of clusters of point defects was found in the area of material damage.
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SURFACE 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 Вячеславовна
In 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.
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DEUTERIUM 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 Микаэлович
Reduced-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.
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Verification of the theory of primary radiation damage by comparison with experimental data
(2019) Majerle, M.; Gann, V. V.; Cizek, J.; Hruska, P.; Ogorodnikova, O. V.; Огородникова, Ольга Вячеславовна
© 2019 Elsevier B.V.Understanding of radiation damage in a solid is important for development of advanced material technologies, namely, for space application, electron microscopy, semiconductor processing, fission and nuclear fusion. Space materials must withstand exposure to high-energy protons. Construction materials of future thermonuclear reactors must withstand exposure to high-energy neutrons. Many properties of materials including mechanical properties are governed by the presence and behavior of lattice defects. Hence, the study of the radiation-induced defects is an important task combining two fields: radiation physics and solid state physics. The paper presents new knowledge on primary defect formation in the main materials for advanced fission and nuclear fusion reactors, bcc tungsten (W) and bcc iron (Fe). The objective of this work is to compare the new experimental data of neutron- and proton-induced defects in W and Fe using well-established method of positron-annihilation lifetime-spectroscopy (PALS) in combination with the literature data with two models of radiation damage, the classical Norgett-Robinson-Torrens (NRT-dpa) model and recently developed athermal recombination corrected (arc-dpa) model. It is shown that experimental data for neutron- and proton-irradiated Fe are better described by arc-dpa model than NRT-dpa model. Whereas experimental data for neutron- and proton-irradiated W are between the NRT-dpa and arc-dpa predictions. The obtained results shed new light on the formation of the primary radiation defects in materials and indicate the need for further development of the theory of radiation damage in a solid.
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Recombination coefficient of hydrogen on tungsten surface
(2019) Ogorodnikova, O. V.; Огородникова, Ольга Вячеславовна
© 2019 Elsevier B.V. The recombination coefficient is an important parameter for modelling hydrogen-metal interaction. It is responsible for hydrogen desorption from the surface of the metal and, therefore, significantly affects the hydrogen penetration into the metal, accumulation in and permeation through the metal. In the present work, the recombination coefficient of hydrogen (H) on tungsten (W) surface is examined. It is shown that the recombination coefficient of H on a clean W surface is extremely high which indicates the rapid desorption of the hydrogen molecule from the surface. Simulation using a high recombination coefficient well describes a wide range of experimental data of gas and ions interaction of hydrogen isotopes with tungsten. Proof of incorrectness of the Anderl's recombination coefficient is presented by comparing it with both theory and experiment.
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Surface 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.
Только метаданные
Annealing 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.
Только метаданные
Influence 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 Вячеславовна
Deuterium (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.
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HYDROGEN 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 Вячеславовна
Interaction 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.