- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Laser-induced spectroscopy and plasma
- Plasma Diagnostics and Applications
- Atomic and Molecular Physics
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Atomic and Subatomic Physics Research
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Spectroscopy and Laser Applications
- Sensor Technology and Measurement Systems
- Nuclear Materials and Properties
- Fault Detection and Control Systems
- Chemical and Physical Properties of Materials
- Particle Detector Development and Performance
- Welding Techniques and Residual Stresses
- Calibration and Measurement Techniques
- Atmospheric Ozone and Climate
- Solid State Laser Technologies
- Magnetic Field Sensors Techniques
- Photonic and Optical Devices
- Electromagnetic Launch and Propulsion Technology
Rosatom (Russia)
2016-2023
Kurchatov Institute
1992-2022
ITER
2021
State Research Center of the Russian Federation
2018-2019
Troitsk Institute for Innovation and Fusion Research
2004-2019
Scientific Research Institute of Technology named after AP Aleksandrov
1997
Lawrence Livermore National Laboratory
1997
General Atomics (United States)
1997
An advanced Thomson scattering system has been built for a linear plasma generator surface interaction studies. The is based on Nd:YAG laser operating at the second harmonic and detection branch featuring high etendue (f/3) transmission grating spectrometer equipped with an intensified charged coupled device camera. able to measure electron density (n(e)) temperature (T(e)) profiles close output of source and, distance 1.25 m, just in front target. enables 50 spatial channels about 2 mm...
Abstract Charge eXchange Recombination Spectroscopy (CXRS) diagnostics are widely deployed in fusion experimental devices for the local measurement of key parameters: ion temperature, rotation velocity and density low-Z impurities. Russian Federation Domestic Agency (RF-DA) developed High-Etendue Spectrometer (HES) designed to fulfill requirements International Thermonuclear Experimental Reactor (ITER) CXRS-edge diagnostics. The HES employs three holographic diffraction gratings that operate...
Recent measurements of the two-dimensional (2-D) spatial profiles divertor plasma density, temperature, and emissivity in DIII-D tokamak [J. Luxon et al., Proceedings 11th International Conference on Plasma Physics Controlled Nuclear Fusion (International Atomic Energy Agency, Vienna, 1987), p. 159] under highly radiating conditions are presented. Data obtained using a Thomson scattering system other diagnostics optimized for measuring high electron densities low temperatures these detached...
The charge exchange recombination spectroscopy (CXRS) diagnostics on the T-10 tokamak is described. system based a diagnostic neutral beam and includes three high etendue spectrometers designed for ITER edge CXRS system. A combined two-channel spectrometer developed simultaneous measurements of two beam-induced spectral lines using same sight. basic element transmitting holographic grating narrow region 5291 ± 100 Å. whole provides impurity spectra Hα line. Ion temperature are routinely...
Impurity transport in the T-10 tokamak plasma with ohmic heating is studied this paper. The values of various impurities densities, measured use passive spectral diagnostics visible (Zeff), active charge exchange measurements (He, C, O), and integral bolometric absolute extreme ultraviolet detectors (Fe, W) are shown. experimental data show that accumulation level growing impurity nuclear determined by parameter , which common for all sorts impurities. Accumulation process neoclassical...
Due to the development of ITER project, requirements technical parameters systems were more precisely and practically determined be at higher levels. The essential increase system characteristics happened recently. A number prototypes manufactured tests carried out. results manufacture 25 systems, subject Russian Federation's obligations in are described.
An overview is given of the present design active beam spectroscopy diagnostics for ITER. Present spatial resolution and signal-to-noise indicate that, in principle, all proposed measurements are possible covering entire plasma minor radius. Calculations show that mirror based periscopes impurity coating first affect signal strength polarization characteristics measured spectra having an impact measurement accuracy. On-line calibration techniques methods to access status addressed.
First experimental results of tungsten transport investigation in OH and ECRH plasmas the T-10 tokamak with W-limiter movable Li-limiter are presented. It is shown that tends to accumulate (a joint process cumulation peaking) near plasma axis ohmic regimes. The W enhanced discharges high values parameter coincides accumulation conditions light medium impurities plasmas. Experiments show immeasurable level Li3+ (0.3–0.5% ne) CXRS diagnostics because low inflow Li respect other impurities....
Active charge exchange recombination spectroscopy (CXRS) is used in most of the present fusion experiments as a proven tool for local measurements main ions plasma [R. Isler, Plasma Phys. Controlled Fusion 36, 171 (1994)]. A comprehensive diagnostic coverage intrinsic and injected impurities essential any self-consistent simulation prediction performance. In particular, assessment helium ash densities [M. von Hellermann et al., 35, 799 (1993)], CXRS will play key role future devices such...
A status report is given on recent joint activities the ITER CXRS and BES diagnostic package. Expected measurement performances are reviewed as well comprehensive discussions led an integral approach to implementation of Core Edge observation periscopes. The “first mirror” location, its operational temperature, maintenance issues, optimization optical imaging addressed. In parallel more technical aspects, particular attention has also been development common evaluation modeling tools. One...
Problems of spectroscopic diagnostics ITER plasma are under consideration. Three types presented: 1) Balmer lines spectroscopy in the edge and divertor plasmas; 2) Thomson scattering, 3) charge exchange recombination spectroscopy. The Zeeman-Stark structure line shapes is discussed. overlapping isotopes H-D-T spectral presented for SOL conditions. polarization measurements H-alpha H-D mixture on T-10 tokamak shown order to separate Zeeman splitting more details. problem background radiation...
КОМПЛЕКС СПЕКТРОСКОПИЧЕСКИХ ДИАГНОСТИК ДЛЯ ИЗМЕРЕНИЯ АБСОЛЮТНОЙ ВЕЛИЧИНЫ И РАДИАЛЬНОГО РАСПРЕДЕЛЕНИЯ ЭФФЕКТИВНОГО ЗАРЯДА ПЛАЗМЫ НА ТОКАМАКЕ Т-10В.А.Крупин 1 , А.Р.Немец Л.А.Ключников К.В.Коробов М.Р
Measurement performance assessment has been carried out for the latest design of ITER Charge Exchange Recombination Spectroscopy (CXRS) Edge diagnostic system. Several plasma scenarios, covering all expected baseline operation regimes ITER, were used. Various impurity (He, Be, C, and Ne) concentrations system whole spatial range (0.5 < r/a 1.0) considered. Statistical errors measurements low-Z temperature, density, rotation velocity calculated. Other non-statistical error sources...
Ion heat conductivity in deuterium plasma of the circular limiter tokamak T-10 is analyzed more than 100 Ohmic shots. Four data scans: density, effective charge, current, and toroidal magnetic field are presented. Each scan formed with preservation other parameters. It shown that at periphery, r/a=0.6−0.8, ion exceeds neoclassical values up to three eight times. The anomalous part χian increases density while it decreases current does not depend on field. highest value observed high-density...
In a magnetically diverted tokamak, the scrape-off layer (SOL) and divertor plasma separates first wall from core plasma, intercepting impurities generated at before they reach plasma. The can also serve to spread heat particle flux over large area of structure using impurity radiation neutral charge exchange, thus reducing peak fluxes strike plate. Such reduction will be required in next generation tokamaks, for without it engineering requirements are very demanding. To successfully...