A5021412831- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Laser-induced spectroscopy and plasma
- Superconducting Materials and Applications
- Solid State Laser Technologies
- Nuclear reactor physics and engineering
- Laser Design and Applications
- Atomic and Subatomic Physics Research
- Particle accelerators and beam dynamics
- Electronic Packaging and Soldering Technologies
- 3D IC and TSV technologies
- Optical Systems and Laser Technology
- Metal and Thin Film Mechanics
- Additive Manufacturing and 3D Printing Technologies
- Diamond and Carbon-based Materials Research
- Atomic and Molecular Physics
- bioluminescence and chemiluminescence research
- Photorefractive and Nonlinear Optics
- Magneto-Optical Properties and Applications
- Radiation Detection and Scintillator Technologies
- Optical and Acousto-Optic Technologies
- Optical properties and cooling technologies in crystalline materials
National Research University of Electronic Technology
2023-2024
ITER
2010-2020
Ioffe Institute
2009-2018
Physico-Technical Institute
2003-2017
Russian Academy of Sciences
2006-2014
Peter the Great St. Petersburg Polytechnic University
2011
State Optical Institute named after SI Vavilov
2008
Forschungszentrum Jülich
2008
Plasma (Russia)
2008
We present here our recent results on the development and testing of first mirrors for divertor Thomson scattering diagnostics in ITER. The system is based several large-scale (tens centimetres) that will be located an area with extremely high (3–10%) concentration contaminants (mainly hydrocarbons) main concern to prevent deposition-induced loss mirror reflectivity spectral range 1000–1064 nm. suggested design mirrors—a high-reflective metal layer a Si substrate oxide coating—combines...
This paper describes the challenges of Thomson Scattering implementation in ITER divertor and evaluates capability to satisfy project requirements related range measured electron temperature density. A number aspects data interpretation are also discussed. Although this assessment proposed solutions considered terms compatibility, they may be some use currently operating magnetic confinement devices.
Almost all optical diagnostic systems in ITER will require the implementation of mirror recovery and protection systems. Plasma cleaning is considered to be most promising technique for removal metal deposits from surfaces. The engineering physical aspects RF discharge application continuous or periodic plasma treatment are discussed with a focus on under conditions. ion flux parameters obtained capacitively coupled (CC) were measured mock-up system. uniformity sputtering CC without magnetic...
The electron component is the main channel for anomalous power loss and indicator of transient processes in tokamak plasma. temperature density profiles mainly determine operational mode machine. This imposes demanding requirements on precision spatial temporal resolution Thomson scattering (TS) measurements. Measurements such high with good accuracy a large fusion device as ITER using TS encounter number physical problems. 40 keV spectrum has significant blue shift. Due to transmission...
The lifetime of front optical components unprotected from reactor grade plasmas may be very short due to intensive contamination with carbon and beryllium-based materials eroded by the plasma beryllium walls tiles. Deposits result in a significant reduction spectral alterations transmission. In addition, even rather thin transparent deposits can dramatically change shape reflectance spectra, especially for mirrors low reflectivity, such as W or Mo. distortion data obtained various...
Experiments and simulations to achieve high values of plasma parameters at the Globus-M spherical tokamak (ST) moderate absolute auxiliary heating power (up 0.8 MW) specific 2–3 MW m −3 ) are described. Important distinguishing features low edge safety factor range, which is unusual for STs, 2.7 < q 5 small plasma–outer wall space (3–5 cm). High ion efficiency with neutral beam injection (NBI) was demonstrated. Results numerical simulation fast trajectories described generation during NBI...
The development of the first mirror cleaning and recovery system is one challenges for all optical diagnostics in ITER. This study focused on capacitively coupled radio frequency (CCRF) discharge as a promising method removal metal deposits. physical aspects RF application are discussed with focus implementation under ITER conditions. effective sputtering rates Be, W Mo were calculated function applied absorbed power noble gases—He, Ne, Ar, Kr, Xe, taking into account complex shape ion...
Abstract Tritium retention inside the vacuum vessel is a potentially serious constraint in operation of large-scale fusion machines like ITER. An situ diagnostics for first wall H/D/T by laser induced desorption spectroscopy (LIDS) proposed use between plasma discharges. The technique based on local baking irradiation and subsequent analysis in-vessel gas optical emission radiation. heating implementation, kinetics thermal extraction accuracy measurements are analysed. To resolve lines...
A divertor Thomson scattering (TS) system being developed for ITER has incorporated proven solutions from currently available TS systems. On the other hand any diagnostic to operate in a hostile environment and very restricted access geometry. Therefore operation an of intensive stray light, plasma background radiation, necessity meet requirement using only 20 mm gap between cassettes diagnosis as well measure temperatures low 1 eV severely constrain design. The challenging this novel which...
МОДЕРНИЗАЦИЯ ДИАГНОСТИКИ ТОМСОНОВСКОГО РАССЕЯНИЯ НА ТОКАМАКЕ ГЛОБУС-МГ.С.Курскиев 1 , С.Ю.Толстяков A.А. Березуцкий В.К.Гусев М
We evaluate using of metal mirrors over‐coated with transparent protection layer for the in‐vessel diagnostic systems in reactor‐grade fusion devices. Ideally, these should satisfy contradictory demands high reflectivity and small rate degradation when being bombarded by CX atoms. The serious threat to performance is surface contamination carbon‐based material eroded from carbon tiles. Via coupling protective a bulk mirror we can mitigate deposit infiuence on reflectance spectra. regards are...
A wide bandpass double-grating polychromator with high rejection and transmission has been designed manufactured for laser-aided plasma diagnostics. The special mount utilizes subtractive dispersion in the second stage of double such that larger is reduced by first stage. This affects intensity stray light background at laser wavelength. edge line was measured 10−5 incident on input slit. At short end 200 nm bandpass, relative approached 10−7.
Abstract Bench tests are used to compare cleaning performance of inductively and capacitively driven radio-frequency (RF) discharges as a potential tool for in-situ maintenance in-vessel diagnostic mirrors in fusion devices. The effect erosion hydrogenated carbon coating is studied different processing conditions. Stainless steel (SS) have been exposed CH4‒Ar H2‒Ar plasmas an RF discharge at pressure 10−2 Torr with input power 0.5 kW 13.6 MHz. samples, which exhibit slow rate chemical...
The ITER design has highlighted the fundamental need to monitor machine operation in more detail. mission of Thomson scattering diagnostics divertor research/operation is discussed with due attention paid challenges and capabilities existing diagnostic design.