V.S. Udintsev

ORCID: 0000-0002-5920-6295
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Fusion materials and technologies
  • Particle accelerators and beam dynamics
  • Nuclear reactor physics and engineering
  • Ionosphere and magnetosphere dynamics
  • Nuclear Physics and Applications
  • Gyrotron and Vacuum Electronics Research
  • Laser-Plasma Interactions and Diagnostics
  • Graphite, nuclear technology, radiation studies
  • Plasma Diagnostics and Applications
  • Physics of Superconductivity and Magnetism
  • Solar and Space Plasma Dynamics
  • Nuclear Materials and Properties
  • Electromagnetic Launch and Propulsion Technology
  • Atomic and Subatomic Physics Research
  • Particle Accelerators and Free-Electron Lasers
  • Nuclear and radioactivity studies
  • Electrostatic Discharge in Electronics
  • Plasma and Flow Control in Aerodynamics
  • Nuclear materials and radiation effects
  • Radiation Detection and Scintillator Technologies
  • Advanced Frequency and Time Standards
  • Electromagnetic Simulation and Numerical Methods
  • Magnetic Field Sensors Techniques

ITER
2015-2024

Technical University of Denmark
2022

Fusion for Energy
2008-2022

University of California, Los Angeles
2013

École Polytechnique Fédérale de Lausanne
2006-2010

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2005-2009

CEA Cadarache
2005-2009

National Agency for New Technologies, Energy and Sustainable Economic Development
2009

Huazhong University of Science and Technology
2008

Institute for Atomic and Molecular Physics
2001-2005

The ITER electron cyclotron (EC) upper port antenna (or launcher) is nearing completion of the detailed design stage and final build-to-print will soon start. main objective this launcher to drive current locally stabilize neoclassical tearing modes (NTMs) (depositing ECCD inside island that forms on either q = 3/2 or 2 rational magnetic flux surfaces) control sawtooth instability (deposit near 1 surface). should be capable steering focused beam deposition location resonant surface over...

10.1088/0029-5515/48/5/054013 article EN Nuclear Fusion 2008-04-08

ITER is an experimental nuclear reactor, aiming to demonstrate the feasibility of fusion realization in order use it as a new source energy. plasma device (tokamak type) which will be equipped with set diagnostic tools satisfy three key requirements: machine protection, control and physics studies by measuring about 100 different parameters. equipment integrated several ports at upper, equatorial divertor levels well internally many vacuum vessel locations. The Diagnostic Systems procured...

10.1088/1748-0221/7/04/c04012 article EN Journal of Instrumentation 2012-04-18

ITER magnetic diagnostics are now in their detailed design and R&D phase. They have passed conceptual reviews a working diagnostic specification has been prepared aimed at the project requirements. This paper highlights specific progress, particular, for in-vessel coils, steady state sensors, saddle loops divertor sensors. Key changes measurement specifications, concept of software electronics also outlined.

10.1063/1.4732077 article EN Review of Scientific Instruments 2012-07-11

This paper describes what we can learn on the regimes of spontaneous electron temperature oscillations discovered in Tore Supra from analysis MHD activity. Since first observations this oscillating behaviour plasma equilibrium, and its interpretation as a predator–prey system involving lower hybrid waves power deposition confinement, modes has confirmed reality safety factor profile oscillations. points towards importance rational values transition to transport barriers reversed magnetic...

10.1088/0029-5515/46/8/005 article EN Nuclear Fusion 2006-07-25

The TCV tokamak facility is used to study the effect of innovative plasma shapes on core and edge confinement properties. In low collisionality L-mode plasmas with electron cyclotron heating (ECH) increases increasing negative triangularity δ. improvement correlates a decrease inner heat transport, even though vanishes core, pointing non-local transport has recently started effects in H-mode plasmas. known improve towards positive triangularity, due increase pedestal height, plagued by...

10.1585/pfr.7.2502148 article EN Plasma and Fusion Research 2012-01-01

The ITER equatorial port visible∕infrared wide angle viewing system concept is developed from the measurement requirements. proposed solution situates 4 systems in ports 3, 9, 12, and 17 with views each (looking at upper target, inner divertor, tangentially left right). This gives sufficient coverage. spatial resolution of divertor 2 times higher than other views. For compensation vacuum-vessel movements, an optical hinge proposed. Compactness low neutron streaming achieved by orienting plug...

10.1063/1.4734487 article EN Review of Scientific Instruments 2012-07-23

The Collective Thomson Scattering (CTS) diagnostic will be a primary for measuring the dynamics of confined fusion born alpha particles in ITER and only alphas below 1.7 MeV [1]. probe beam CTS comes from 60 GHz 1 MW gyrotron operated ~100 Hz modulation sequence. In plasma, probing scattered off fluctuations primarily due to ions. Seven fixed receiver mirrors pick up radiation (the signal) seven measurement volumes along covering cross section plasma. is planned provide temporal resolution...

10.1051/epjconf/201920303002 article EN cc-by EPJ Web of Conferences 2019-01-01

The ITER Collective Thomson scattering (CTS) diagnostic will measure the dynamics of fusion-born alpha particles in burning plasma by a 1 MW 60 GHz gyrotron beam off fast-ion induced fluctuations plasma. have seven measurement volumes across cross section and resolve particle energies range from 300 keV to 3.5 MeV; importantly, CTS is only capable measuring confined for below ∼1.7 MeV also be sensitive other populations. temporal resolution 100 ms, allowing capture on that timescale, typical...

10.1063/5.0101867 article EN Review of Scientific Instruments 2022-10-01

The 110 GHz and the new 140 gyrotron systems for electron cyclotron resonance heating (ECRH) ECCD on TEXTOR are described results of ECRH experiments with system reported. Central Ohmic plasmas shows presence an internal transport barrier near q = 1. This is confirmed by modulated experiments. A central also indicated in radiatively improved (RI) mode discharges up to two barriers seen during current ramp phase. control sawteeth reported both RI target plasmas.

10.1088/0029-5515/43/11/009 article EN Nuclear Fusion 2003-11-01

ITER will explore a plasma parameter envelope currently not available in tokamaks. This require set of diagnostics that can follow this envelope. To implement these reliable and robust way requires development current techniques many areas to make them applicable ITER: they need be operable the environment satisfy physics engineering requirements. In some cases, exploitation new required. While much work has been carried out area, significant further remains bring system implementation.

10.1109/sofe.2011.6052210 article EN 2011-06-01

Small-scale structures with high poloidal mode numbers (m=10-20) have been observed in the TEXTOR tokamak plasma pulsed radar reflectometry and an electron cyclotron emission diagnostic, conjunction large 2/1 1/1 islands. The small islands a peaked density profile, similar to that of simultaneously large-scale This together observation high-frequency temperature fluctuations are very pronounced near X points hints strongly perturbed magnetic topology around points.

10.1103/physrevlett.94.085001 article EN Physical Review Letters 2005-03-03

Considerable progress has been made on the design of ITER electron cyclotron emission (ECE) diagnostic over past two years. Radial and oblique views are still included in order to measure distortions momentum distribution, but view redirected reduce stray millimeter radiation from heating system. A major challenge designing 1000 K calibration sources remotely activated mirrors located ECE shield module (DSM) equatorial port plug #09. These critical systems being modeled prototypes developed....

10.1051/epjconf/201714702003 article EN cc-by EPJ Web of Conferences 2017-01-01

High frequency (> 100 kHz) modes have been observed for the first time in combined LHCD and ICR-heated minority H (D) plasmas on Tore Supra by means of a correlation ECE diagnostic fluctuation reflectometers. These identified as toroidicity-induced Alfven eigenmodes (TAEs) that are destabilized fast hydrogen ions with energies above 250 keV. In reversed central shear non-linear oscillations temperature, evolution TAE is linked to development local safety factor. This confirms temperature...

10.1088/0741-3335/48/3/l02 article EN Plasma Physics and Controlled Fusion 2006-02-17

The baseline design for the ITER electron cyclotron emission (ECE) diagnostic has entered detailed preliminary phase. Two plasma views are planned, a radial view and an oblique that is sensitive to distortions in momentum distribution near average thermal momentum. Both provide high spatial resolution temperature profiles when remains Maxwellian. ECE system consists of front-end optics, including two 1000 K calibration sources, equatorial port plug EP9, 70-1000 GHz transmission from...

10.1051/epjconf/20158703002 article EN cc-by EPJ Web of Conferences 2015-01-01
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