- Fusion materials and technologies
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Iron and Steelmaking Processes
- Vacuum and Plasma Arcs
- Metallurgical Processes and Thermodynamics
- Industrial Engineering and Technologies
- Combustion and Detonation Processes
- Laser Design and Applications
- Ecology and biodiversity studies
- Nuclear Physics and Applications
- Metallurgical and Alloy Processes
- Metal Extraction and Bioleaching
- Magnetic confinement fusion research
- nanoparticles nucleation surface interactions
- Optical Coatings and Gratings
- Mining and Gasification Technologies
- Inorganic Fluorides and Related Compounds
- Superconducting and THz Device Technology
- Electric Power Systems and Control
- Material Properties and Applications
- X-ray Diffraction in Crystallography
- Gyrotron and Vacuum Electronics Research
Budker Institute of Nuclear Physics
2016-2025
Siberian Branch of the Russian Academy of Sciences
2016-2025
Novosibirsk State University
2016-2024
Gipronickel Institute
2003-2024
Peoples' Friendship University of Russia
2024
Russian New University
2024
KazMunayGas (Kazakhstan)
2023
Novosibirsk State Technical University
2016-2022
Boreskov Institute of Catalysis
2022
Academy of Sciences of the Republic of Sakha
2020
A test facility developed at the Budker Institute is designed for experimental simulation of effects ITER-scale transient heat loads on plasma facing materials. Employing a long-pulse electron beam creation transients has advantages low direct pressures surface material and lesser limitation power density by vapor shielding. In addition, relative modest attendant background light allows using set diagnostics observation erosion dynamics. The includes fast imaging in near infrared, scattering...
Abstract A boron carbide coating, deposited on tungsten using the detonation spraying method, was tested under high pulse number transient heat loads expected during ITER tokamak H-mode operation. The were relevant to those caused by edge localized modes (ELMs) and mitigated disruptions. results showed that in case of ELM-like heating first wall zone tokamak, coating is capable withstand ∽10 4 pulses before detachment from substrate. In thermal shocks with more intense plasma disruptions or...
A test facility for experimental simulation of transient heat loads in ITER divertor with the use high power electron beam is developed at Budker Institute Nuclear Physics. This report presents an study absorption incident flux 10-50 GW/m2 on area about 2 cm2 a tungsten target. The has duration 0.1-0.3 ms and energy 80-95 keV, Diagnostics measuring parameters target are briefly discussed. Results measurement profile calorimetry deposited sample ELM-like load presented.
For simulation of radiation effects and defects in the Ni-Al system, a new many body potential was developed by joining equilibrium part Mishin's EAM with universal function Ziegler, Biersack Littmark at suitable interatomic spacing corresponding pairwise energy from DFT calculations. To assess qualities this potential, we performed molecular dynamics simulations to calculate threshold displacement pure metals Ni, Al their NiAl B2 phase superalloy ambient temperature. It found that nickel is...
Experimental research on behavior of rolled tungsten plates under intense transient heat loads generated by a powerful (a total power up to 7 MW) long-pulse (0.1–0.3 ms) electron beam with full irradiation area 2 cm2 was carried out. Imaging the sample fast CCD cameras in NIR range and illumination 532 nm continuous-wave laser applied for in-situ surface diagnostics during exposure. In these experiments were exposed 0.5–1 MJ/m2 flux factor (Fhf) close above melting threshold at initial room...
A novel BETA test facility (Beam of Electrons for materials Test Applications) was developed at the Budker Institute to study erosion directly during impact intense thermal shocks. powerful (up 7 MW) long pulse (100–300 μs) electron beam is applied experimental simulation fast transient heat loads with intensity probable in ITER divertor. The flux parameter on a target can be widely varied (FHF = 10–300 MW m−2 s0.5) from value significantly below melting threshold much higher, within area...
Wide-area (2 cm2) high-power (up to 7 MW) submillisecond electron beam source was applied for generation of intense pulsed heat loads on tungsten sample. Various diagnostics sets were used in-situ research the surface damage: IR imaging front view target, capturing reflection pattern continuous wave laser radiation, recording intensity thermal radiation from several spots surface. Sample exposed a various near and above melting threshold. Formation crack network its development with...
В статье рассматриваются элементы технической политики государственной компании «Российские автомобильные дороги», направленные на совершенствования управления автомобильными дорогами в течение всего жизненного цикла с помощью современных технологий информационного моделирования. Рассматриваются промежуточные итоги выполняемой настоящее время по заказу ГК «Автодор» научно-исследовательской работы «Разработка рекомендаций использованию инновационных моделирования всех этапах автомобильных дорог».
New generations of fusion devices need alternative plasma-facing materials. The currently approved material composition for the first wall and divertor ITER tokamak has a number disadvantages: insufficient resistance to thermal shock, sputtering microparticles into plasma high atomic Z armor material. A promising but largely untested idea is proposal use high-temperature ceramics as materials most heat-loaded components new-generation devices. Among advantages are low enough intense heating....
A test facility for experimental simulation of transient heat load expected ELMs type I events in ITER is developed at BINP SB RAS. Dynamics tungsten particles the ablation plume investigated by small-angle light scattering technique and using fast CCD ICCD cameras. The threshold intense particle generation, sizes velocities ejected from surface are estimated.
A problem of surface melting under the impact plasmas is one most important in development future magnetic confinement fusion reactors. The expected high heat loads can lead to tungsten chosen as material a divertor and first wall ITER. melt move action forces quickly deform surface. This article shows that at temperatures, vapor be considered conductive with conductivity enough taken into account during simulation current through sample. We describe mechanism generation by thermo-emf due...
A new test facility for experimental simulation of transient heat load expected in the ITER divertor during unmitigated events is developed. Application a long-pulse (0.1–0.3 ms) wide-aperture (up to 2 cm2) electron beam as heating device provides powerful energy loads at tungsten target with FHF> 250 MJ m−2 s−0.5. Dynamics particles ablation plume investigated novel PSI experiments small-angle laser light scattering technique. The threshold intense droplet generation and dynamics sizes are...
Electron beam appears to be a good instrument for the simulation of heat loads because low pressure material and large depth shielding layer, allowing application higher loads. This work is focused on theoretical numerical modeling heating tungsten by plasma flow electron clarify differences in process. The time necessary vapor development found both them. Essential between beams with various energies were found. It was explained significant cooling evaporation at one stages. surface...
The dynamics of the diffraction peak shape during pulsed heat load on mosaic single-crystal tungsten were measured at `Plasma' scattering station eighth beamline VEPP-4 synchrotron radiation source Budker Institute Nuclear Physics. observed evolution agrees with theoretical predictions based calculations deformation caused by heating. Three clearly distinguishable stages diffraction-peak found, correlating temperature and distributions. residual plastic increased subsequent heating pulses.
The paper presents an overview of plasma-material interaction studies at the Siberian Synchrotron and Terahertz Radiation Centre. measurements recrystallization surface texturing are demonstrated. growth grain size after exposure by electron beam was detected using two-dimensional diffractometry. orientation crystal structure in tungsten irradiated deuterium plasma. residual stresses were measured. predicted deformations pulsed heat load is confirmed. First in-situ experiments confirmed...
Hihg-power flows of plasma cause mechanical destruction materials via non-uniform deformation and stresses. The possibility synchrotron radiation scattering diagnostics is discussed. experiments at the new station "Plasma" on VEPP-4M demonstrated measurements change in diffraction angle during pulsed heating.