A5067247579- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Rocket and propulsion systems research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Solar and Space Plasma Dynamics
- Energetic Materials and Combustion
- Advanced Power Generation Technologies
- Engineering and Environmental Studies
- Atomic and Molecular Physics
- Coal Combustion and Slurry Processing
- Field-Flow Fractionation Techniques
- Material Properties and Applications
- Laser-induced spectroscopy and plasma
- Advanced Data Processing Techniques
- Radiative Heat Transfer Studies
- Combustion and flame dynamics
- Industrial Engineering and Technologies
- Laser Design and Applications
- Scientific Measurement and Uncertainty Evaluation
- Astrophysics and Star Formation Studies
V.I. Vernadsky Crimean Federal University
2023
Scientific Research Institute of Polymer Material (Russia)
2015-2021
Perm State University
2010
Peter the Great St. Petersburg Polytechnic University
1994-2004
Japan Atomic Energy Agency
2003
Max Planck Society
1994-2002
Max Planck Innovation
2002
Max Planck Institute for Plasma Physics
1994
Institute of Physics
1993
St Petersburg University
1992-1993
Abstract The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and preparation operation, as well addressing issues for a future DEMO design. Since 2015, AUG equipped with new pair 3-strap ICRF antennas, which were designed reduction tungsten release during operation. As predicted, factor two on ICRF-induced W plasma content could be achieved by sheath voltage at antenna limiters via compensation image currents central side straps in...
Recent experiments at ASDEX Upgrade have achieved advanced scenarios with high βN (>3) and confinement enhancement over ITER98(y, 2) scaling, HH98y2 = 1.1–1.5, in steady state. These discharges been obtained a modified divertor configuration for Upgrade, allowing operation higher triangularity, changed neutral beam injection (NBI) system, more tangential, off-axis deposition. The figure of merit, βNHITER89-P, reaches up to 7.5 several seconds plasmas approaching stationary conditions....
An on-line predictor of the time to disruption has been installed on ASDEX Upgrade tokamak. It is suitable either for avoidance disruptions or mitigation those that are unavoidable. The prediction uses a neural network trained eight plasma parameters and their derivatives extracted from 99 disruptive discharges. was tested off-line over 500 discharges found work reliably be able predict majority disruptions. on-line, 128 used inject killer pellets mitigate loads.
The closed ASDEX Upgrade Divertor II, `LYRA', is capable of handling heating powers up to 20 MW or P/R 12 MW/m, owing a reduction the maximum heat flux target plates by more than factor 2 compared with open I. This caused high radiative losses from carbon and hydrogen inside divertor region in agreement B2-EIRENE modelling predictions. At medium densities H mode, type I ELM behaviour shows no dependence on method (NBI, ICRH). Upgrade-JET dimensionless identity experiments showed...
Ion and electron temperature profiles in conventional L H mode on ASDEX Upgrade are generally stiff limited by a critical gradient length ∇T/T as given ion (ITG) driven turbulence. ECRH experiments indicate that (Te) also stiff, predicted turbulence with streamers. Accordingly, the core edge temperatures proportional to each other plasma energy is pedestal pressure for fixed density profiles. Density not confinement improves peaking. Medium triangularity shapes (δ<0.45) show strongly...
The ablation of carbon pellets injected into ECR-heated plasmas Wendelstein 7-AS (W7-AS) has been investigated using a photographic technique with the aim studying features process in stellarator plasmas. rate profiles were measured assuming proportionality C II radiation and rate. This assumption was confirmed experimentally by simulations performed quasi-three-dimensional code. fraction continuum radiation, which is detected together line (when light filters finite spectral width), did not...
The authors present experimental evidence and an analysis of two phenomena arising during carbon pellet ablation-a toroidal trajectory deflection enhanced localized ablation in the electron cyclotron resonance (ECR) current drive regime. A model developed for describing a tokamak shows that curvature is sensitive to density. Photography used as diagnostic determination local density ohmically heated plasma. Directly measured profiles using pellets are reasonable agreement with obtained...
Impurity confinement behaviour has been studied by using a deposition probe in conjunction with pellet injection. Generally, an exponential decay of the impurity efflux and nearly symmetric ion/electron side toroidal flows have observed. During phases strong plasma disturbances, asymmetric flow is seen, indicative edge transport prompt recycling from local sources. The application ECRH may cause such disturbances.
The paper contains recent results in the field of pellet diagnostics obtained on T-10 and ASDEX-Upgrade tokamaks (collaboration between STU IPP) a proposal to inject high Z impurity pellets for control disruption ramp-down phase ITER.
The design, construction, and the testbed results for a novel compact gas gun injector solid diagnostic pellets of different sizes materials is reported here. was optimized requirements ASDEX Upgrade tokamak, yielding possibility widely varying deposition profile ablated material inside plasma. This allows variation pellet velocity total number injected atoms. use spherical carbon propellant gases (He,N2,H2) in an accessible range from about 150 m/s to more than 600 masses 2×1018 1020 Both...
ДЛЯ ПОВЫШЕНИЯ ПРОИЗВОДИТЕЛЬНОСТИ ВЫЧИСЛЕНИЙ ПРИ ЧИСЛЕННОМ МОДЕЛИРОВАНИИ ФУНКЦИОНИРОВАНИЯ СЛОЖНЫХ ТЕХНИЧЕСКИХ СИСТЕМ На примере расчета логически сложной прикладной задачи -численного моделирования переходных внутрикамерных процессов при выходе на режим работы ракетного двигателя твердого топлива -приводится сравнение вычислительной производительности рабочей станции, оснащенной мощным многоядерным центральным процессором (CPU INTEL Core i7 4790K LGA 1150), без применения и с применением...
ЧИСЛЕННОЕ МОДЕЛИРОВАНИЕ ВНУТРИКАМЕРНЫХ ПРОЦЕССОВ ПРИ ВЫХОДЕ НА РЕЖИМ РАБОТЫ РАКЕТНОГО ДВИГАТЕЛЯ ТВЁРДОГО ТОПЛИВА
This contribution presents recent results of pellet technologies development for plasma fuelling in magnetic confinement machines with open or closed configuration. The current status ITV7 injector GOL3 multimirror linear machine, PGS2.2 guide system ITV4 in-situ TUMAN-3M tokamak and ITV5 centrifuge Globus-M spherical is reported. New on modeling tangential injection into are discussed as well.