A5038147673- Magnetic confinement fusion research
- Laser-Plasma Interactions and Diagnostics
- Fusion materials and technologies
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Advanced Image Processing Techniques
- Atomic and Subatomic Physics Research
- Nuclear Physics and Applications
- Image and Video Quality Assessment
- Metal and Thin Film Mechanics
- Image Processing Techniques and Applications
- Digital Media Forensic Detection
- Vacuum and Plasma Arcs
- Solar and Space Plasma Dynamics
- Particle Detector Development and Performance
- Graphite, nuclear technology, radiation studies
- Magnetic Properties and Applications
- Visual Attention and Saliency Detection
- Electric Motor Design and Analysis
- Laser-induced spectroscopy and plasma
- Fault Detection and Control Systems
- Advanced Vision and Imaging
- Advanced Data Processing Techniques
Kurchatov Institute
2005-2025
Lomonosov Moscow State University
2023
The results of electron current drive experiments on the T-10 tokamak are presented. total RF power was up to 2.5 MW, temperature 7 keV and maximum driven 110 kA. efficiency ηCD approximately 0.1 A/W. value its dependence plasma parameters agree satisfactorily with linear theory, corrected for finite confinement time resonant electrons. In discharges large beta poloidal, βp ≈ 3, complete replacement inductive by noninductive cyclotron bootstrap obtained
Poloidal asymmetry and radial correlation lengths of turbulence were investigated in T-10 at low field side high by reflectometry. Correlation plasma confinement with the type was observed. Improvements heavy ion beam probe diagnostic enabled us to measure potential during electron cyclotron resonance heating (ECRH) a wide range positions operational regimes. The appeared rotate close E × B velocity. concept internal transport barrier (e-ITB) formation low-order rational surfaces under...
The plasma stability and confinement have been investigated through control of the safety factor profile q(r) by electron cyclotron current drive in T-10 tokamak. regimes with dq/dr≅0 dq/dr<0 core were obtained. Various types MHD activity observed: ordinary sawtooth, saturated humpbacks, hills etc. It was shown that when minimal value qmin increases from <1 to = 2 becomes strongly unstable due corresponding or passes steady-state improved mode. latter is realized internal transport barrier...
High density experiments were carried out in T-10 with gas puffing and electron cyclotron resonance heating (with absorbed power value up to 1.4 MW) oblique perpendicular launch. Densities exceeding the Greenwald limit (nGw) by a factor of 1.8 achieved regime high edge safety at current flat-top, q(a)≅8.2. The decrease q(a) 3 led reduction ratio (e) lim /nGw 1. Confinement degradation increase was not significant limit. However, typical linear energy confinement time saturates e⩾0.6nGw. This...
The results of the electron cyclotron heating (ECH) experiments in T-10 are presented. An 11-tube gyrotron set-up with a total power 4 MW was used experiments. consists two types gyrotrons different wavelengths. dependence energy confinement on RF deposition profile investigated. temperature reactor level obtained.
Results of the electron cyclotron current drive experiment at second harmonic resonance on T-10 tokamak are presented. High frequency (HF) power up to 1.2 MW was launched from low field side. A maximum driven 35 kA and efficiency ηCD = 0.05 A/W an temperature Tc(O) 4 keV a density nc(0) 1 × 1013 cm-3 were obtained. For HF power, less than predicted by linear theory unless effect elliptical polarization non-perpendicular injection is considered, in which case close theoretical value. The...
The study of two types T-10 regime-a regime with low impurity confinement (S regime) and a enhanced (B has been continued in deuterium discharges ne approximately necrit. In the present experiments transitions from S to B regimes is obtained by method gas puff cut-off. Detailed investigations profile evolution Te(r), Ti(r), ne(r) carbon density nc showed, that greatly changes after cut-off, while Te(r) Ti(r) remain practically unchanged at central zone plasma. This indicates possibility...
Two types of electrode biasing H-mode were observed on the T-10 tokamak in regimes with electron–cyclotron resonant heating (ECRH). These differ mainly by dynamics electron temperature. Both are characterized a strong (130 V cm−1) radial electric field formation, decrease Dα emission intensity, rise line-average plasma density and an increase energy confinement time. However, distinguishing features type II time delay 70–80 ms temperature growth, slower density, weak drop intensity. The...
T-10 experiments with electron internal transport barrier (ITB) formation in discharges reverse shear q(r) profile are described. Reverse magnetic was formed the central region characterized by r/aL ⩽ 0.3. It is shown that thermal conductivity decreases essentially comparison value typical for L-mode. found degradation of ITB correlates development MHD activity part plasma column.
In order to obtain breakdown and suitable plasma parameters for low-voltage OH start-up, high level of EC-power was injected into T-10 tokamak. Input HF-power varied in the range 0.15–1.0 MW. Two HF-launcher systems with different output beams allowed inject EC-waves maximum power density 0.25 MW/cm2 0.01 MW/cm2. Dependence time delay on obtained. It shown, that optimal were achieved presence equilibrium currents I=3 kA (input HF-power=1.0 MW). Electron temperature Te=100÷150 eV electron...
The detailed design of the magnetic diagnostic for ITER is presented. system consists groups pickup coils and flux loops on vessel wall, back plate, divertor. These sensors provide measurements equilibrium reconstruction fluctuation analysis. supplemented by Rogowski halo current a diamagnetic loop. complete meets measurement requirements, matching those contemporary large divertor tokamaks. maximum radiation exposure such that will survive lifetime ITER.
Experiments on second harmonic electron cyclotron current drive were done the T-10 tokamak using four gyrotrons. Total powers up to 1.2 MW at a frequency of 140 GHz injected. Current generation by (EC) waves was demonstrated in experiments. The efficiency η and its dependence plasma parameters measured it shown that is nonlinear function input power, more closely predicted Fokker–Planck calculations than linear theory. interaction EC with tail distribution be important. It also found density...
Cрывы разряда в крупных токамаках и будущих реакторах являются серьёзной проблемой, ограничивающей срок их службы.Представлены результаты исследований влияния напуска благородных газов на динамику развития срыва токамаке Т-10.Срывы вызывались разными способами: наращиванием плотности плазмы до предельной и/или инжекцией дейтериевой или примесной (углеродной) макрочастицы.Инжекция (гелия, аргона ксенона) проводилась как стационарной стадии для инициации разряда, так во время спада...
Non-traditional scheme of HF-injection has been used in T-10 tokamak for ECRH at the 2nd harmonic ECR X-mode. Two HF-launcher systems, with focusing beams, injected power opposite directions under toroidal angles +/-20˚. Input from each launcher was about same (P hf =0.8 ÷ 0.85MWt). Absorbed energy deposed central area plasma column. The new phenomenon found some shots W-limiter and Li-coating regime mentioned above. spontaneous rise electron density nearly all column occurs simultaneously...
A main goal in developing video-compression algorithms is to enhance human-perceived visual quality while maintaining file size. But modern video-analysis efforts such as detection and recognition, which are integral video surveillance autonomous vehicles, involve so much data that they necessitate machine-vision processing with minimal human intervention. In cases, the codec must be optimized for machine vision. This paper explores effects of compression on recognition (objects, faces,...