A5076989616- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Magnetic Bearings and Levitation Dynamics
- Particle Accelerators and Free-Electron Lasers
- Electric Motor Design and Analysis
- Nuclear Physics and Applications
- Electromagnetic Launch and Propulsion Technology
- Magnetic Properties and Applications
- Ionosphere and magnetosphere dynamics
- Electric Power Systems and Control
- Geomagnetism and Paleomagnetism Studies
- Non-Destructive Testing Techniques
- Magnetic Properties of Alloys
- Nuclear reactor physics and engineering
- Atomic and Subatomic Physics Research
- Heat Transfer and Numerical Methods
- Structural mechanics and materials
- Radiation Therapy and Dosimetry
- Magnetic and Electromagnetic Effects
- Advanced Power Generation Technologies
- Atomic and Molecular Physics
- Plasma Diagnostics and Applications
- High-pressure geophysics and materials
D.V.Efremov Institute of Electrophysical Apparatus (Russia)
2011-2024
St Petersburg University
2016-2023
ITER
2011
An analysis has been carried out to study error fields anticipated in the ITER machine. The were simulated with use of a computer code, PRORCODE, developed at Efremov Institute. Fourier decomposition was performed on equilibrium rational magnetic surfaces inside plasma filament evaluate lower modes (m,n) = (1,1), (2,1), (3,1). Major sources field associated misalignments magnet system tokamaks are discussed.
Error fields in tokamak magnet systems are primarily associated with displacements of toroidal field and poloidal coils, arising during their manufacture assembly. The Fourier analysis error on a rational magnetic flux surface, anticipated the ITER machine, exhibited lower-order modes ((m, n)=(1,1), (2,1), (3,1)) as most crucial ones. A statistical study using Monte Carlo simulations has demonstrated that an averaged three-mode from superposition coil can be two to three times higher than...
A computation technology has been developed as a tool to provide accurate and detailed magnetostatic simulations for tokamaks. Calculation algorithms are described which allow modelling of complex magnet systems with regard electromagnetic compatibility their components subsystems. The efficiency the proved in computations typical test blanket module International Thermonuclear Experimental Reactor.
Electromagnetic suspension (EMS) system for magnetically levitated vehicles can utilize different types of magnets, such as room temperature electromagnets, superconducting magnets well permanent magnets. In the course study trichotomy has been applied to electromagnetic system. The EMS configuration considered in this paper treated a combination these three modelled individually. Results computations were compared measurements on working prototype that provided stable levitation platform...
Abstract On ITER, plasma start-up will be performed in limiter configuration on the inboard equatorial beryllium first wall panels (FWP). In contrast to most present tokamaks, however, this ramp-up phase comparatively long (∼10 s) and use of actively cooled components means that power flux management is key if FWP lifetime not compromised. Shaping FWPs mandatory ensure leading edges do appear between neighbouring units. For ITER panels, has been optimized account for discovery recent years...
The stray magnetic field produced by the ITER tokamak complex, including effect of ferromagnetic materials in building structures, has been studied. results obtained show that fields can be significantly modified structures areas distant from tokamak. It is shown complex exceed 100 Gs where service staff are possibly located. Such a level should agreement with medical and safety engineering limits as well to ensure normal operations equipment sensitive fields. presented form set maps, which...
The problem of complex thermohydraulic simulation the magnet system International Thermonuclear Experimental Reactor using VINCENTA modelling is discussed. results validation are presented on basis an experiment with central solenoid model coil.
A unified method is proposed for numerical simulation of magnet systems complex configurations, which contain permanent magnets and electric currents. The based on the use a reduced scalar magnetic potential (the "T-Omega" method). Numerical simulations with computer code KOMPOT allow magnetostatic analysis precision taking into account non-linear properties materials. comparison calculated measured data presented test sample.
The specific characteristics of the numerical simulation 3-D magnetostatic problems taking into account geometric complexity magnet systems and nonlinear character equations describing magnetic field are considered on basis KOMPOT program package. results calculations tokamak synchrotron different in iron saturation requirements precision given. attained accuracy has been confirmed by comparing result with data obtained measurements other methods.< <ETX...
Abstract The error fields produced by localized steel objects in the ITER tokamak building have been studied this paper. critical mass of objects, producing plasma region ‘3-mode’ field 0.1 Unit (10−6 toroidal magnetic field), is estimated for a set object positions. It shown that scaled with distance as R 7, if R≥30 m. Keywords: tokamaklocalized elementmagnetic surfaceerror
The paper briefly describes the main results of numerical simulation and analysis transient electromagnetic processes for plasma discharge scenario 3106 in GLOBUS-M tokamak (at Ioffe Physical–Technical Institute, Russia). A developed two-dimensional model uses a parametric representation boundary assuming parabolic distribution current density over cross-section.
Abstract The stray magnetic fields produced at plasma initiation (in particular the gas breakdown (BD)) by ITER tokamak complex building have been studied. influence of global elements is estimated. scenario was designed and simulated using virtual coils with currents producing a field in BD region similar to that from building. Keywords: ITERtokamakmagnetic fieldferromagnetic materialstray
The discreteness of the toroidal field (TF) coils causes toroidally asymmetric perturbations magnetic (TF ripple). Maximum value TF ripple produced in plasma by ITER is 1.16%. requirements are determined loss fast particles and potential changes H-mode characteristics. particle behavior well known a maximum at separatrix <;1% enough to avoid excessive losses all scenarios. quantitative influence on performance remains subject continuing R&D this time prudent approach make as small reasonably...
Abstract Perturbations of the axial symmetry a toroidal magnetic field, or field (TF) ripple, in tokamaks can potentially lead to losses high-energy particles from plasma. These be significant and are one major concerns with respect both energy blance deuterium–tritium plasma heat load limits International Thermonuclear Experimental Reactor (ITER). In ITER design, ferromagnetic inserts used reduce TF ripple. this work impact on ripple is analysed optimize their filling factor within design...
Abstract Error fields produced by the ferromagnetic rebar of building ITER tokamak complex have been studied. It is shown that ‘3-mode’ error field global asymmetry about 2×10−6 toroidal magnetic field. Analysis caused local elements was performed for one nearest to structure, bioshield. bioshield produces an less than 10−5 Such are acceptable. Keywords: tokamaktokamak complexmagnetic surfaceerror
A feasibility has been demonstrated for numerical reconstruction of geometrical displacement or deformations the winding occurred in manufacture and assembly magnet coils using magnetic measurements, that is one principal issues quality control magnet. For validations proposed approach, test results possible misalignments deviations ITER coil are presented.