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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Огородникова
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Ольга Вячеславовна
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19 results
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- ПубликацияТолько метаданныеDeuterium retention in tungsten pre-damaged by ELM-like high heat flux plasma and sequentially irradiated with deuterium ions(2024) Harutyunyan,Z.; Ogorodnikova,O.V.; Umerenkova,A.; Ostojic,N.; Efimov,V.; Nikitin,A; Sergeechev,A.; Арутюнян, Зорий Робертович; Огородникова, Ольга Вячеславовна; Умеренкова, Анастасия Сергеевна; Остойич, Никола; Ефимов, Виталий Сергеевич; Никитин, Александр Александрович; Сергеечев, Антон Александрович
- 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 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 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.
- ПубликацияТолько метаданныеVerification 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.
- ПубликацияТолько метаданныеRecombination 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.
- 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 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 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 метаданныеRadiation-induced effects in self-passivating W-Cr-Y alloy(2024) Ogorodnikova, O. V.; Nikitin, A. A.; Rogozkin, S. V.; Sal, E.; Gasparyan, Y. M.; Огородникова, Ольга Вячеславовна; Никитин, Александр Александрович; Рогожкин, Сергей Васильевич; Гаспарян, Юрий Микаэлович