Взаимодействие ионов с поверхностью (ВИП)

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01_Том 1_XXVI Международная конференция Взаимодействие ионов с поверхностью «ВИП-2023»
(НИЯУ МИФИ, 2023)
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01_Том 2_XXVI Международная конференция Взаимодействие ионов с поверхностью «ВИП-2023»
(НИЯУ МИФИ, 2023)
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ABLATION OF HIGH-Z MATERIAL DUST GRAINS IN EDGE PLASMAS
(НИЯУ МИФИ, 2015) Marenkov, E.; Krasheninnikov, S.; Маренков, Евгений Дмитриевич
Nowadays it is well recognized that dust particles can play an important role in fusion plasma performance and material transport [1]. Therefore, it is important to have a good understanding of the most important processes dust grains encounter in the course of the interactions with fusion grade plasmas. Many fundamentals of grain-plasma interactions were developed by dusty-plasma community. However, grain-plasma interactions in fusion devices have some important distinctions. In particular, in hot and dense fusion plasma environment dust grains ablate rather quickly. The effect of the vapor on grain-plasma interactions can only be neglected for relatively small grains (below ~10 microns). Meanwhile, it is important to know how the vapor “shielding” alters grain-plasma interactions for larger (~100 microns) grains, which may pose significant threat for plasma performance and even result in disruption, especially for the case where these are high-Z material grains.
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ALUMINIUM OXIDATION IN PLASMA OF ABNORMAL GLOW DISCHARGE
(НИЯУ МИФИ, 2023) Pisarev, A. A.; Tarasyuk, G. M.; Borisyuk, P. V.; Isaenkova, M. G.; Lebedinskii, Yu. Yu.; Zaripova, M. M.; Исаенкова, Маргарита Геннадьевна; Писарев, Александр Александрович; Тарасюк, Григорий Михайлович; Борисюк, Петр Викторович; Лебединский, Юрий Юрьевич
Aluminum oxide layers in all its various forms have become widespread due to the unique combination of properties that can be modified by varying the conditions of their growth. The alumina layer can either be applied to the substrate by chemical and physical methods or grown by oxidation. For practical purposes, layers of various thicknesses and structures are needed. The standard method for obtaining thick (of the order of 100-1000 nm) porous layer is electric arc anodization in weak electrolytes. The standard method for obtaining thin (about 10 nm) layers is thermal oxidation. Dense layers of intermediate thickness are difficult to obtain by such methods. There are few papers in the literature that investigate the possibility of obtaining oxide layers with a thickness of tens of nanometers by oxidizing aluminum in oxygen plasma [1-5]. The description of the kinetics of the oxidation process in those works was given on the basis of the assumption of the diffusion character of oxygen transfer from the surface into the interior of the metal. This approach is absolutely unsuitable for description the transport of oxygen and aluminum through the oxide layer, since both oxygen and aluminum in the oxide are in the form of ions, and an electric charge is formed on the surface of the dielectric facing the plasma, so that the transport of oxygen coming from the plasma must occur under by the action of an electric field in the oxide dielectric layer. In this work, experiments on plasma enhanced oxidation (PEO) were carried out on the oxidation of aluminum in the anomalous glow discharge oxygen plasma, which provides uniform treatment over the entire surface of samples of arbitrary shape. Also, a simple model was proposed for description of the oxidation kinetics, taking into account oxygen transport in the electric field.
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ANALYSIS OF ION FLUXES IN LINEAR PLASMA DEVICES
(НИЯУ МИФИ, 2015) Sorokin, I. A.; Vizgalov, I. V.; Bidlevich, O. A.; Сорокин, Иван Александрович
Analysis of both ion mass-spectrum and plasma parameters is very important for plasma-surface interaction experiments to control discharge regime and ion composition. In linear plasma devices with a magnetic field, it is possible to apply a static mass-spectrometer using magnetic field of plasma device to ion separation with focusing at 180 or 360 degree.
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ANALYTICAL EXPRESSION FOR THE SHEATH ELECTRIC FIELD FOR SPUTTERING MODELLING AT JET ILW EXPERIMENTS
(НИЯУ МИФИ, 2017) Borodkina, I.; Borodin, D.; Brezinsek, S.; Tsvetkov, I. V.; Kurnaev, V. A.; Klepper, C. C.; Lasa, A.; Guillemaut, C.; Jacquet, P.; Stamp, M. F.; Giroud, C.
The study of plasma–surface interaction processes is important for a successful realization of the international ITER project. The JET ITER-like wall (ILW) [1] comprises a tungsten (W) divertor and beryllium (Be) main chamber wall thus matching the material configuration planned for ITER. Estimating plasma facing component (PFC) sputtering by plasma ions is an important issue for ITER as erosion determines the life time of PFC, impacts on the tritium retention by co-deposition with Be and leads to an increase of impurities in core plasma and the consequent reduction in fusion plasma performance. For correct calculation of the sputtering yields for PFCs the accurate expression for the sheath electric field must be included. This work represents the review of our previous works devoting to the development of analytical expressions for the sheath electric field taking into account the presence of an oblique magnetic field, secondary electron-electron emission and surface biasing.
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ANGULAR DISTRIBUTION OF W SPUTTERED BY LOW ENERGY AR
(НИЯУ МИФИ, 2017) Sorokin, I.; Marenkov, E.; Nordlund, K.; Eksaeva, A.; Маренков, Евгений Дмитриевич; Сорокин, Иван Александрович
Sputtering of the first wall tokamak materials by low energy of the order of 100 eV but high fluxes, 1020 cm-2s-1 is one of the main mechanisms responsible for steady-state first wall erosion. At such low energies sputtering occurs due to few-collision cascades. The resulting angular and energy distributions of sputtered particles are different from cosine and Thompson distributions predicted by kinetic theory of cascades valid at larger energies. Experimental data on the distributions for materials and energies of interest are scarce [1]. At the same time experiments at linear plasma devices demonstrated that the distributions play a substantial role in comprehension of the sputtered particles transport in plasma [2]. In this work we develop an experimental procedure for direct measurements of the angular distributions of the sputtered particles and a method for molecular dynamics calculation of them. The proposed simulation procedure accurately accounts for polycrystalline structure of the samples.
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APPLICATION OF KEV-ENERGY PROTON SCATTERING FOR SURFACE ANALYSIS
(НИЯУ МИФИ, 2019) Bulgadaryan, D.; Sinelnikov, D.; Kurnaev, V.; Efimov, N.; Ефимов, Никита Евгеньевич; Синельников, Дмитрий Николаевич
Low- and medium-energy ion scattering (LEIS/MEIS) are widely used techniques of surface analysis [1–4]. Conventional LEIS/MEIS setups utilize noble gas ions and electrostatic energy analyzers that makes these methods very sensitive to composition of the uppermost atomic layers of an analyzed sample. However, high neutralization probability of noble gas ions restricts LEIS/MEIS depth profiling capabilities [5]. The use of hydrogen ions with lower neutralization probability instead of noble gas provides possibility to measure the thickness of surface layer if its atomic mass is very different from that of underlying target, that is the case e.g. in nanoelectronics [6] or for redeposition of plasma-facing materials in fusion devices [7]. In this work we present simulated and experimental data on implementation of keV-energy proton scattering (KEPS) for surface analysis.
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APPLICATION OF LIBS, LA-QMS, LA-TOF-MS FOR FUSION RELEVANT MATERIALS ANALYSIS
(НИЯУ МИФИ, 2021) Efimov, N. E.; Sinelnikov, D. N.; Bulgadaryan, D. G.; Gasparyan, Y. M.; Vovchenko, E. D.; Marenkov, E. D.; Маренков, Евгений Дмитриевич; Ефимов, Никита Евгеньевич; Вовченко, Евгений Дмитриевич; Синельников, Дмитрий Николаевич; Гаспарян, Юрий Микаэлович
One of the critical issues on the way to controlled nuclear fusion is related to plasma wall interaction. Such interaction leads to co-deposition of hydrogen isotopes together with eroded first wall materials. It is known that the deuterium-tritium (DT) mixture will be used in ITER and future fusion devices as a fuel. So as the accumulation of radioactive tritium in the machines is limited by the nuclear license, there is a need for some remote fuel retention monitoring system. In current devices, the total fuel amount is determined from the gas balance (difference between input and output flows) measurements and from a post mortem analysis of plasmafacing components. One of the most promising techniques which can be applied in situ in tokamaks is based on laser irradiation of the surface of interest followed by mass- or optical spectroscopy. Such a technique was already applied in TEXTOR tokamak to the hydrogenic carbon layers [1], and it is included in the task list of ITER with a high priority.
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CHARACTERISATION OF PLASMA PARAMETERS OF INDUCTIVELY - COUPLED PLASMA SOURCE AND ITS APPLICATION FOR NITRIDING OF STEELS
(НИЯУ МИФИ, 2015) Meshcheryakova, E.; Zibrov, M.; Kaziev, A.; Khodachenko, G.; Pisarev, A.; Казиев, Андрей Викторович; Писарев, Александр Александрович
Inductively coupled plasma (ICP) sources are widely used in many technological applications, including etching of semiconductors, thin film deposition, and surface modification of materials [1]. In particular, ICP plasmas could be attractive for plasma nitriding of metals (steels, titanium, aluminium, etc.) due to the following features: high ionization degree (up to several percent), low pressure (down to 10−4 mbar) that results in increase of energy of ions bombarding a substrate and reduction of their energy spread, and relatively small impurity content in the plasma due to electrodeless nature of the discharge. Consequently, thorough characterization of plasma parameters in ICP sources is essential for revealing the optimal regimes of plasma nitriding.
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COMPARISON OF EROSION AND DEPOSITION IN JET DURING CARBON AND ITER-LIKE CAMPAIGNS
(НИЯУ МИФИ, 2015) Krat, S.; Gasparyan, Yu.; Pisarev, A.; Mayer, M.; de Saint-Aubin, G.; Bykov, I.; Coad, P.; Likonen, J.; van Renterghem, W.; Ruset, C.; Widdowson, A.; JET-EFDA, contributors; Гаспарян, Юрий Микаэлович; Крат, Степан Андреевич; Писарев, Александр Александрович
Erosion of plasma facing elements in fusion devices is an important question affecting their lifetimes. Redeposition of eroded materials may lead to accumulation of hydrogen isotopes, which makes it an important problem from the perspective of radiological safety. Redeposition in layers with carbon and beryllium could be a channel for hydrogen isotope accumulation.
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CORRELATION OF DEUTERIUM RETENTION WITH CRYSTALLINE STRUCTURE IN DENSE AND DISORDERED TUNGSTEN COATINGS
(НИЯУ МИФИ, 2017) Ogorodnikova, O. V.; Ruset, C.; Dellasega, D.; Pezzoli, A.; Passoni, M.; Sugiyama, K.; Gasparyan, Yu.; Efimov, V.; Ефимов, Виталий Сергеевич; Гаспарян, Юрий Микаэлович; Огородникова, Ольга Вячеславовна
Dense nano-structured tungsten (W) coatings are used as plasma-facing materials in current tokamaks and thick coatings are suggested to be used also for the future fusion devices, ITER and DEMO. In this study, deuterium (D) retention in various W coatings was investigated to understand dependences of the D retention on the crystalline structure of each W coating and on the substrate material.
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DETERMINATION OF HYDROGEN BINDING ENERGIES WITH DEFECTS IN METALS FROM THERMAL DESORPTION MEASUREMENTS WITH DIFFERENT HEATING RATES
(НИЯУ МИФИ, 2015) Zibrov, M.; Gasparyan, Yu.; Shubina, A.; Pisarev, A.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович
Investigation of hydrogen isotope behaviour in plasma-facing and structural components is of great importance for successful development of fusion reactors with magnetic confinement. The hydrogen inventory (especially in the metals with a positive heat of solution) is determined by the presence of defects, which act as trapping sites for hydrogen. Therefore precise determination of defects’ parameters, namely binding energies for hydrogen atoms and their concentration is essential. Thermal desorption spectroscopy (TDS) is a commonly used method for such purposes. The trap parameters are usually determined by fitting of simulated TDS spectra to experimental ones using numerical diffusion-trapping codes, such as TMAP7 [1]. In such approach, the determination of the characteristics of the trapping sites is ambiguous – they act as free parameters in the model and, as a result, one spectrum can be fitted by using several combinations of parameters.
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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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Deuterium trapping in co-deposited layers of ITER-relevant materials
(НИЯУ МИФИ, 2021) Krat, S. A.; Prishvitsyn, A. S.; Vasina, Ya. A.; Fefelova, E. A.; Gasparyan, Yu. M.; Pisarev, A. A.; Писарев, Александр Александрович; Гаспарян, Юрий Микаэлович; Крат, Степан Андреевич; Пришвицын, Александр Сергеевич
Hydrogen isotope accumulation in fusion devices is a serious problem. Because deuterium-tritium mixture will be a working gas in future fusion devices, including ITER tokamak, tritium accumulation is an issue from the perspective of radiation safety. In total, only 700 grams of tritium are allowed to be present in ITER vessel at any time, with additional 120 in the cryopumps, and 180 grams allocated to measurement error, to the total of 1000 grams.
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ERO-PSI CODE FOR NUMERICAL SIMULATION OF EXPERIMENTS ON TUNGSTEN SPUTTERING IN LINEAR PLASMA DEVICE PSI-2
(НИЯУ МИФИ, 2015) Eksaeva, A. A.; Marenkov, E. D.; Borodin, D.; Kirshner, A.; Laenger, M.; Kurnaev, V. A.; Kreter, A.; Маренков, Евгений Дмитриевич
Plasma-wall interaction is one of the recognized issues for thermonuclear reactor performance and seems to be a key direction in fusion researches in the framework of the ITER project [1]. Tungsten (W) has been chosen as a main material for construction of ITER divertor due to its low sputtering at edge plasma temperatures, large melting temperature, and small uptake of tritium.
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ESTIMATES OF He+ SCATTERED FROM THE SURFACE SURVIVAL PROBABILITY USING BINARY COLLISIONS CODES
(НИЯУ МИФИ, 2019) Mamedo, N. V.; Kurnaev, V. A.; Sinelnikov, D. N.; Mamedov, I. M.; Синельников, Дмитрий Николаевич; Мамедов, Никита Вадимович
Low-energy (1-20 keV) ion scattering spectroscopy is the widespread method of surface analysis [1,2]. The surface layer composition can be reconstructed from narrow peaks in the energy spectra of the scattered inert gas ions and recoil ions [3]. The main advantage of the surface analysis using inert gas ions is the high sensitivity to the first layer of surface atoms. This is due to the low initial energy of the ions (and therefore small ion penetration depth) and the high neutralization probability of the reflected ions, which increases with the penetration depth of the incident particle into the solid [3]. However, for quantitative surface analysis, it is extremely important to determine the neutralization probability (or the probability of ion survival), since this method usually detects reflected ions only.
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EXCITATION OF THE ELECTRONIC SYSTEM OF SUBSURFACE LAYERS OF TIO2 IRRADIATED WITH SWIFT HEAVY IONS
(НИЯУ МИФИ, 2017) Rymzhanov, R. A.; Medvedev, N. A.; Volkov, A. E.
A swift heavy ion (SHI, E=1-10 MeV/nucl) penetrating through a solid deposits the largest part of its energy into the electronic subsystem of the target. Further kinetics of lattice excitation in the nanometric vicinity of the ion trajectory (ion track) depends crucially on achieved parameters of the disturbed electronic system.
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FABRICATION OF FINE-DISPERSED COATINGS AT DEPOSITION WITH SIMULTANEOUS SPUTTERING
(НИЯУ МИФИ, 2015) Rogov, A. V.; Martynenko, Yu. V.; Kapustin, Yu. V.; Belova, N. E.; Мартыненко, Юрий Владимирович
New low temperature method of homogeneous Mo nanocrystallite coating formation was developed. The coating was formed at magnetron Mo deposition on polished Mo polycrystalline substrate with simultaneous ion sputtering. Deposition and sputtering were performed in combined discharge of magnetron – hole cathode [1]. X-ray difractometry and SEM were used for coating structure investigation. A theoretical model was developed for coating formation by proposed method. At low excess of deposition rate over sputtering rate uncontrolled fast growth of some Mocrystallites is effectively suppressed, being fine dispersed coating is formed. Such coatings can be used as a radiation stable reflecting coatings for high temperature plasma diagnostic mirrors [2, 3]. The proposed method can be used also for other materials modification, semiconductors included.
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FUTURE DIRECTIONS IN EDGE PLASMA PHYSICS AND PLASMA MATERIAL INTERACTIONS IN FUSION DEVICES: SOME RESULTS FROM THE FES COMMUNITY PLANNING WORKSHOPS 2015
(НИЯУ МИФИ, 2015) Krasheninnikov, S. I.
In February 2015, Dr. Ed Synakowski, USDOE FES Associate Director, has announced a set of Community Planning Workshops that are intended to seek community engagement and input for future program planning activities (see the website https://www.burningplasma.org/activities/article=FES%20Community%20Planning%20Wor kshops%202015). Particular objectives of the workshops are: discussion of near- and longterm research tasks, such as experiments that could be performed on existing experimental facilities; possible upgrade of existing facilities and diagnostics capabilities that would enable of enhance the research tasks; identification of areas for which modeling and simulations could be impactful. In my talk I’ll present some results from two of these workshops, scheduled to take place in May-June 2015, which are aimed on the physics of edge plasma and plasma-material interactions in fusion devices.