Персона:
Огородникова, Ольга Вячеславовна

Организационные подразделения

Организационная единица

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.

Фамилия

Огородникова

Имя

Ольга Вячеславовна

Полная страница элемента

Результаты поиска

Теперь показываю 1 - 8 из 8

Открытый доступ
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.
Открытый доступ
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.
Открытый доступ
Positron 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.
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.
Только метаданные
Helium 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 Александрович
Helium (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.
Только метаданные
Deuterium 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 Викторович
The 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.
Только метаданные
Deuterium 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.
Только метаданные
Effect 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.