Персона: Беграмбеков, Леон Богданович
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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 доступPlasma-induced formation of hydrogen resistant oxide layers on zirconium surface(2019) Gumarov, A. I.; Kashapov, N. F.; Luchkin, A. G.; Vakhitov, I. R.; Evsin, A. E.; Begrambekov, L. B.; Kaplevsky, A. S.; Kudashev, I. S.; Евсин, Арсений Евгеньевич; Беграмбеков, Леон Богданович© Published under licence by IOP Publishing Ltd.Features of plasma-induced formation of the surface oxide layers on zirconium alloy E110 (Zr-1%Nb) as well as hydrogen resistant properties of these layers are studied. It is shown that irradiation of the E110 sample with 1 keV ions of He + O2 plasma produces the oxide layer depleted by oxygen nearby the surface. The onset of the intensive hydrogen penetration into the ion-irradiated sample during the steam test (673 K, 0.1 MPa) appears to occur 1500 hours later than into the untreated one.
- ПубликацияОткрытый доступBehaviour of Redeposited Tungsten Layers with Varying Impurity Content during Thermal and Radiation Loads(2019) Begrambekov, L. B.; Bidlevich, O. A.; Grunin, A. V.; Puntakov, N. A.; Voityuk, A. N.; Беграмбеков, Леон Богданович; Пунтаков, Николай Алексеевич© Published under licence by IOP Publishing Ltd.Tungsten is going to be implemented as a material for plasma-facing divertor tiles in an ITER tokamak. Accumulation of dust particles due to exfoliation of redeposited tungsten layers can severely affect the operation of a fusion devices. Behaviour of tungsten films deposited on tungsten, including layers with added impurities of iron (0,2 at.% and 2 at.% concentration), as well as dust particles with Al impurity, has been studied. It is shown that a film with 2 at.% impurity of iron exhibits exfoliation and blistering when exposed to thermal and radiation loads, while tungsten dust particles with aluminium impurity undergo various structural changes depending on their Al content when heated.
- ПубликацияОткрытый доступBehavior of B4C coating on tungsten under exposition on T-10 tokamak plasma(2019) Begrambekov, L. B.; Grunin, A. V.; Sadovsky, Ya. A.; Беграмбеков, Леон Богданович; Садовский, Ярослав Алексеевич© Published under licence by IOP Publishing Ltd.It was shown (Buzhinsky, 2003) that in situ renewable coating of boron carbide can protect the tiles of the divertors of thermonuclear facilities from destruction and also to prevent accumulation of remarkable amounts of tritium in the plasma facing materials. In the paper presented a plasma method for deposition of boron carbide coating with a high adhesion to tungsten was developed. In the laboratory installation boron carbide coating on tungsten was subjected to cycling irradiation by the deuterium ion flux with power density up to 5.0 MW/m2 in the temperature range up to 1500 K. The results of the tests showed that the composition, integrity and adhesion of the coating were not violated in the laboratory tests. In the T-10 tokamak the behavior of the coating was investigated in the temperature range up to 3600 K when irradiated with plasma power in the range of 20-100 MW/m2 during plasma disruption. Being irradiated in T-10 tokamak, the coating retained its continuity, adhesion and protected tungsten from the effect of the even at temperatures of 2500-3600 K, when the coating melted under irradiation and its composition changed to B:C ≈ 1:1.
- ПубликацияОткрытый доступО ВОЗМОЖНОСТИ УМЕНЬШЕНИЯ ТЕРМОДЕСОРБЦИИ ИЗ ТИТАНА В ПРОЦЕССЕ ИОННОГО ОБЛУЧЕНИЯ(НИЯУ МИФИ, 2015) Каплевский, А. С.; Беграмбеков, Л. Б.; Двойченкова, О. А.; Евсин, А. Е.; Захаров, А. М.; Шигин, П. А.; Захаров, Андрей Михайлович; Беграмбеков, Леон Богданович; Евсин, Арсений ЕвгеньевичPeculiarities of hydrogen ions interaction with titanium deuteride layer were studied. It was shown that deposition of yttrium oxide layer decreases hydrogen isotopes desorption from titanium layer. Decreasing of deuterium desorption from titanium deuteride under irradiation by hydrogen ions with low energy (<1000 eV) was observed. It was observed even in that case when pulses of irradiation with high energy ions combined with penetration of ions with the energy lower than 1000 eV into the surface.
- ПубликацияОткрытый доступПЛАЗМЕННЫЕ МЕТОДЫ СОЗДАНИЯ ПОВЕРХНОСТНЫХ СЛОЕВ НА ЦИРКОНИИ, ПРЕПЯТСТВУЮЩИХ ПРОНИКНОВЕНИЮ ВОДОРОДА(НИЯУ МИФИ, 2015) Евсин, А. Е.; Беграмбеков, Л. Б.; Гордеев, А. А.; Евсин, Арсений Евгеньевич; Беграмбеков, Леон Богданович; Гордеев, Алексей АлексеевичThe results of steam tests (T=400°C, p=1 bar) of two methods of protection of zirconium against hydrogenation – plasma irradiation and deposition of yttrium coatings – are discussed. Amount of hydrogen in irradiated sample after 2500 h of exposure to overheated steam was 5 times less than the corresponding value for unirradiated one. Amount of hydrogen in the sample with yttrium coating was almost constant during 4000 h of exposure.
- ПубликацияОткрытый доступГАЗИФИКАЦИЯ И УДАЛЕНИЕ ПЕРЕНАПЫЛЕННЫХ УГЛЕРОДНЫХ СЛОЁВ ИЗ ПЛАЗМЕННЫХ УСТАНОВОК ВОЗДЕЙСТВИЕМ КИСЛОРОДНО- ОЗОНОВОЙ СМЕСЬЮ(НИЯУ МИФИ, 2015) Айрапетов, А. А.; Беграмбеков, Л. Б.; Садовский, Я. А.; Садовский, Ярослав Алексеевич; Айрапетов, Алексей Александрович; Беграмбеков, Леон БогдановичThe results of gasification rate measurements of carbon films and carbonfiber composite (CFC) under the influence of ozone-oxygen mixture are presented. Gasification rate was found to be 0.4-0.6 μm/hour (220-250 0С, 0.3 bar, 0.6 at% ozone) in case of planar sample and 1 and 2 mm gap with stainless steel walls and 1 mm gap with CFC wall; 15 μm/hour for planar CFC sample (250 0С, 1 bar, 10 at% ozone).
- ПубликацияОткрытый доступCharacteristics of the modification of the near-surface layer and sputtering of graphite under high intensity ion irradiation(2020) Puntakov, N. A.; Begrambekov, L. B.; Grunin, A. V.; Пунтаков, Николай Алексеевич; Беграмбеков, Леон Богданович© Published under licence by IOP Publishing Ltd.In this paper, features of the modification of near-surface layer of R6510P100D01 grade graphite under irradiation by deuterium and helium ions at a temperature of 2050 °C is investigated. It is shown that irradiation by such ions at a flux density of 1,4×1018 ion/cm2s initiates vacancy transport from the irradiated surface to the bulk of the sample, leading to the formation of a porous layer inside the sample with a thickness of over 2 mm. High sputtering yields, exceeding those for irradiation by the same ions at room temperature with a moderate intensity ion fluxes, lead to the conclusion that in these conditions, sublimation is the main mechanism of the removal of carbon atoms from the surface of graphite.
- ПубликацияОткрытый доступProperties of graphite to be used as a material for the T-15MD tokamak plasma-facing elements(2020) Grashin, S. A.; Arkhipov, I. I.; Puntakov, N. A.; Ayrapetov, A. A.; Begrambekov, L. B.; Grunin, A. V.; Dovganyuk, S. S.; Kaplevskiy, A. S.; Tenishev, A. V.; Пунтаков, Николай Алексеевич; Айрапетов, Алексей Александрович; Беграмбеков, Леон Богданович; Довганюк, Сергей Сергеевич; Тенишев, Андрей Вадимович© Published under licence by IOP Publishing Ltd.The results of the measurement of physical properties, sputtering yield during irradiation by hydrogen ions and a study of surface morphology modification of graphite to be used for the plasma-facing materials of the T-15MD tokamak are presented in this work.
- ПубликацияОткрытый доступУДАЛЕНИЕ ДЕЙТЕРИЯ, ВНЕДРЁННОГО В ГРАФИТ, ПРИ ПОСЛЕДУЮЩЕМ ОБЛУЧЕНИИ ИОНАМИ ВОДОРОДНОЙ ПЛАЗМЫ(НИЯУ МИФИ, 2017) Айрапетов, А. А.; Беграмбеков, Л. Б.; Довганюк, С. С.; Каплевский, А. С.; Айрапетов, Алексей Александрович; Довганюк, Сергей Сергеевич; Беграмбеков, Леон БогдановичThe paper investigates peculiarities of deuterium removal implanted into graphite by subsequent irradiation with hydrogen plasma ions. It is shown that irradiation with 50-eV hydrogen ions leads to desorption of deuterium previously implanted with energies 100 and 650 eV. The fraction of deuterium remaining in graphite decreases with the increase of hydrogen irradiation dose. The amount of deuterium in graphite stays constant after multiple cycles of consequent irradiation. Conclusion is made that low energy irradiation with hydrogen ions can be used as a method of low temperature graphite degassing.
- ПубликацияТолько метаданныеDevelopment of Quality Tungsten Coating on Ceramics as a Microwave Shield for ITER High-Frequency Magnetic Sensor(2020) Ma, Y.; Vayakis, G.; Shigin, P.; Walsh, M.; Begrambekov, L.; Gordeev, A.; Sadovsky, Y.; Zakharov, A.; Беграмбеков, Леон Богданович; Гордеев, Алексей Алексеевич; Садовский, Ярослав Алексеевич; Захаров, Андрей Михайлович© 2019, © 2019 American Nuclear Society. High-quality tungsten coating deposition on sintered aluminum nitride ceramic substrates (both of thin flat chips and structural boxes) was realized using an adapted plasma-aided coating deposition rig. The tungsten coating produced using this technique and the accompanying apparatus setup are of high-purity, strong adhesion, and controlled three-dimensional uniformity (<20% thickness variations). The coating also exhibits well-structured and smooth (Ra < 1.0 µm) microscopic surface landscape with densely clustered tungsten granulations. The coated samples were tested under load conditions expected during ITER operation, including thermal cycling and superheated (up to 500°C) steam. Exposure to thermal cycles and hot steam made no apparent changes to the coating’s microscopic structure with no sign of cracks, blistering, or exfoliation seen under electron microscopy. These successes validated the microwave shield design for the ITER high-frequency magnetic sensor, which is based on this concept, and laid a solid foundation for the production of this component in the forthcoming procurement phase. Besides, a failure test was conducted for the tungsten coating in the temperature range of 500°C to 1500°C. Surface smoothing, pores, delamination, and mass loss in substrate were observed when temperature exceeded 1000°C, possibly due to the evaporation of aluminum atoms. These findings unveiled the changes of tungsten coating properties under extreme conditions that are of both academic and practical values.