A. Alekseev

ORCID: 0000-0002-8914-8575
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About
Contact & Profiles
Research Areas
  • Superconducting Materials and Applications
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Particle accelerators and beam dynamics
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Spectroscopy and Laser Applications
  • Nuclear Physics and Applications
  • Advanced Chemical Physics Studies
  • High-pressure geophysics and materials
  • Geotechnical and Geomechanical Engineering
  • Spacecraft and Cryogenic Technologies
  • Molecular Spectroscopy and Structure
  • Photochemistry and Electron Transfer Studies
  • Inorganic Fluorides and Related Compounds
  • Laser Design and Applications
  • Quantum, superfluid, helium dynamics
  • Electromagnetic Launch and Propulsion Technology
  • Particle Accelerators and Free-Electron Lasers
  • Advanced materials and composites
  • Analytical Chemistry and Sensors
  • Nuclear and radioactivity studies
  • Advanced Energy Technologies and Civil Engineering Innovations
  • Electric Motor Design and Analysis
  • Magnetic Field Sensors Techniques

Centre for Forest Ecology and Productivity
2024

ITER
2012-2018

D.V.Efremov Institute of Electrophysical Apparatus (Russia)
1997-2013

University of Wuppertal
2011

Lomonosov Moscow State University
2007

"VNIINM" named after AA Bochvar
1996-1998

Pushkin Leningrad State University
1990

State Optical Institute named after SI Vavilov
1981

The targeted plasma parameters of the compact spherical tokamak (ST) Globus-M have basically been achieved. reasons that prevent further extension operating space are discussed. operational limits together with an understanding limiting form basis for defining design requirements next-step, Globus-M2. recent experimental and theoretical results achieved discussed, problems research programme summarized finally, Globus-M2 presented. magnetic field current in will be increased to 1 T 0.5 MA,...

10.1088/0029-5515/53/9/093013 article EN Nuclear Fusion 2013-08-16

The first series components of large D-shaped toroidal field coils (TFC) on the ITER Tokamak project are being fabricated and assembled at European Fusion for Energy (F4E) Japanese Domestic Agency (JADA) premises since 2013. TF magnet system consists 18 individual connected in based a Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn cable-in-conduit conductors supplied by 68-kA rated current with an overall 41-GJ stored energy peak...

10.1109/tasc.2016.2536640 article EN IEEE Transactions on Applied Superconductivity 2016-03-01

Abstract A necessity to address a wide spectrum of engineering problems in ITER determined the need for efficient tools modeling magnetic environment and force interactions between main components magnet system. The assessment operating window machine, by electro-magnetic (EM) forces, check feasibility particular scenarios play an important role ensuring safety exploitation. Such analysis-powered prevention damages forms element Machine Operations Investment Protection strategy....

10.1088/0029-5515/55/8/083022 article EN Nuclear Fusion 2015-07-21

Abstract The density of valence states for fluorite‐type crystals is calculated on the basis tight‐binding (TB) and OPW methods. More precisely energy values bands determined by TB method at high‐symmetry points Γ, X, L are reported. A comparison made with other theoretical estimates experimental data.

10.1002/pssb.2221030232 article EN physica status solidi (b) 1981-02-01

The ITER Vacuum Vessel (VV) features upper, equatorial and lower ports. Although the port design has been overall completed in past, of some remaining interfaces was still progress finalized now. As construction phase started, procurement VV ports launched. upper will be procured by Russian Federation DA, while Korean DA. main industrial suppliers were selected development manufacturing is Since classified at nuclear level N2, manufacture its components are to compliant with French code...

10.1109/sofe.2013.6635447 article EN 2013-06-01

Currently reconstruction is initiated on the T-15 tokamak at Institute of Tokamak Physics, NRC “Kurchatov Institute”. The purpose to build facility with a small aspect ratio , elongated cross-section and divertor major radius 1.67 m, long plasma current pulse 2 MA up 10 s powerful auxiliary heating (up 15 MW). intended for demonstration steady-state burning high parameters physics research support ITER program development volumetric neutron sources. involves replacement existing...

10.1109/tasc.2012.2185474 article EN IEEE Transactions on Applied Superconductivity 2012-02-10

The main functions of the ITER Vacuum Vessel (VV) are to provide necessary vacuum for plasma operation, act as first nuclear confinement barrier and remove heating. design VV has been reviewed in past two years due more advanced analyses, modifications required by interfacing components R&D. Following signature four Procurement Arrangement (PAs), manufacturing sectors, ports In-Wall Shielding (IWS) is being finalized fabrication sectors started 2012.

10.1109/sofe.2013.6635466 article EN 2013-06-01

A review of fifty Russian environmental geoservices implemented using open source software by governmental and commercial scientific organizations, universities individuals has been carried out. The role in the implementation interdisciplinary cooperation between various research groups presentation projects’ results is shown. Geoservices are organized according to their application associated with Unified System State Environmental Monitoring (USSEM). Functional capabilities libraries used...

10.47148/1609-364x-2024-4-4-20 article EN Geoinformatika 2024-12-16
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