A5050160121- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Solar and Space Plasma Dynamics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Atomic and Molecular Physics
- Laser-induced spectroscopy and plasma
- Geomagnetism and Paleomagnetism Studies
- Dust and Plasma Wave Phenomena
- Theoretical and Computational Physics
- Vacuum and Plasma Arcs
- Earthquake Detection and Analysis
- Gas Dynamics and Kinetic Theory
- Atomic and Subatomic Physics Research
- Characterization and Applications of Magnetic Nanoparticles
- Nuclear Materials and Properties
- Tropical and Extratropical Cyclones Research
- Magnetic Field Sensors Techniques
- Quantum, superfluid, helium dynamics
- Electromagnetic Launch and Propulsion Technology
- Electric Power Systems and Control
Peter the Great St. Petersburg Polytechnic University
2016-2025
Plasma (Russia)
2024
Moscow Engineering Physics Institute
2003-2021
ITER
2021
Ioffe Institute
2012
D.V.Efremov Institute of Electrophysical Apparatus (Russia)
2011
Culham Science Centre
2004-2010
Polytec (Germany)
2008
Max Planck Society
2001-2007
National Centre of Scientific Research "Demokritos"
2005
The understanding and predictive capability of transport physics plasma confinement is reviewed from the perspective achieving reactor-scale burning plasmas in ITER tokamak, for both core edge regions. Very considerable progress has been made understanding, controlling predicting tokamak across a wide variety conditions regimes since publication Physics Basis (IPB) document (1999 Nucl. Fusion 39 2137–2664). Major areas considered here follow. (1) Substantial improvement content, reliability...
• Reviews the fundamental physics aspects of first ITER W divertor and defines required operational lifetime within Staged Approach. Uses SOLPS simulation database to establish target peak heat flux neutral pressure burning plasma operating domain. Assesses consequences narrow SOL channels, fluid drifts, component shaping 3D magnetic fields for ELM control. recrystallization define an budget shows that fluxes ∼50% higher than previously assumed may be acceptable. Shows Ne N should equally...
Abstract The B2‐Eirene code package was developed to give better insight into the physics in scrape‐off layer (SOL), which is defined as region of open field‐lines intersecting walls. SOL characterised by competition parallel and perpendicular transport defining this a 2D system. description plasma‐wall interaction due existence walls atomic processes are necessary ingredients for an understanding layer. This paper concentrates on basic combining results with experiments analytical models or...
The Globus-M spherical tokamak has demonstrated practically all of the project objectives during 15-year period operation. main factor limiting further progress in plasma performance is a relatively low toroidal magnetic field. maximum field achieved on was 0.4 T with exception limited number shots 0.55 T, which led to damage coil 2002. increase up 1.0 together current 0.5 MA will result significant enhancement operating parameters upgraded Globus-M2 machine. experimental program be focused...
Abstract The non-linear reduced four-field RMHD model in cylindrical geometry was extended to include plasma rotation, neoclassical poloidal viscosity and two fluid diamagnetic effects. Interaction of the static resonant magnetic perturbations (RMPs) with rotating plasmas tokamaks studied. self-consistent evolution equilibrium electric field due RMP penetration is taken into account model. It demonstrated that pedestal region steep pressure gradients, mean flows perpendicular field, which...
Impurity seeding into a tokamak divertor for radiative cooling is considered as tool achieving detached/semi-detached regimes required to meet the condition of acceptable heat loads on plates.Experiments aimed at searching operational window with significant reduction poloidal fluxes due impurity radiation and without decreasing confinement are performed many tokamaks.Critical issue in these experiments which fraction impurities retained region extracted upstream scrape-off layer (SOL).In...
Using the new version of SOLPS plasma boundary code package, SOLPS-ITER, paper presents first ever simulations ITER burning baseline H-mode edge with drifts and currents activated.Neon (Ne) seeded discharges for divertor power dissipation are considered.The results scrape-off layer (SOL) parameters without compared, both SOLPS-ITER against earlier SOLPS-4.3modelling (which did not include a drift description) constituting bulk existing simulation database.Whereas effect on equatorial...
A complete system of transport equations with all the important perpendicular currents is derived for simulation tokamak edge plasma. These are implemented in B2.5 code and solved parameters ASDEX Upgrade tokamak. The relative roles different mechanisms transverse conductivity formation potential profile studied. It demonstrated that a reasonable distribution plasma can be obtained without an ad hoc assumption existence anomalous conductivity. role E × B drifts redistribution closing analysed.
A new B2SOLPS5.2 transport code has been developed and implemented for the simulation of H-mode shots. equation system is proposed, which equivalent to was used in B2SOLPS5.0 previously. The main idea replace major part large radial ∇ B driven convective fluxes by poloidal with same divergence both particle balance energy equations. This special importance where diffusion coefficient strongly reduced inside barrier flows are undesirable from numerical point view. shots ASDEX-Upgrade MAST...
It is well known that usual assumptions of neoclassical theory become invalid if very large gradients occur at the plasma edge. Therefore rotation in tokamaks revisited order to account for anomalous transport driven by a turbulence. shown this model yields both steep and gradual profiles poloidal velocity edge corresponding H L regimes confinement, respectively. Results conclusions are focused on experiments employing biased electrode technique. Regimes with fast excess sound speed...
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,...
The first experiments on noninductive current drive (CD) using lower hybrid waves in a spherical tokamak are described. Waves at 2.45 GHz were launched by 10 waveguide grill with 120° phase shift between neighbouring waveguides. experimental results for novel poloidal slowing-down scheme CD efficiency is found to be somewhat larger than that predicted theoretically whilst the same time being less standard CD. Geodesic acoustic modes (GAM) have been discovered Globus-M. GAMs localized 2–3 cm...
The 2D equation system for an ionized ablatant density integrated along the magnetic field lines and a polarization potential is solved numerically. pellet modelled by plasma source of given intensity spatial dimensions. effects non-uniform tokamak are taken into account. It has been shown that vertical drift current inside produces causes in direction major radius. resulting E*B drifts lead to rather complicated cloud shape resembling 'mushroom' with two clouds connected narrow 'stem'....
Impurity deposition and mixing during gas jet-initiated plasma shutdown is studied using a rapid ({approx}2 ms), massive ({approx}10{sup 22} particles) injection of neon or argon into stationary DIII-D H-mode discharges. Fast-gated camera images indicate that the bulk jet neutrals do not penetrate far pedestal. Nevertheless, high ({approx}90%) thermal quench radiated power fractions are achieved; this appears to be facilitated through combination fast ion heat transport, both driven by...
The impact of resonant magnetic perturbations (RMPs) on the structure edge transport barrier has been studied. A model for density pump-out mechanism during stochastization plasma is proposed. observed phenomena are explained as a result ambipolar electric field, which modified RMP, particle fluxes in pedestal region. It demonstrated that rise inside leads to effect density, while temperature increases spite big electron heat conductivity stochastic field. latter not sufficient change...
Abstract A systematical study of <?CDATA $\vec {E}\times \vec {B}$ ?> drift and parallel current effects is reported based on the analysis simulations by B2SOLPS5.2 transport code. It demonstrated that divertor asymmetry caused or amplified poloidal thermal current.
Major developments on the Mega Amp Spherical Tokamak (MAST) have enabled important advances in support of ITER and physics basis a spherical tokamak (ST) based component test facility (CTF), as well providing new insight into underlying physics. For example, L–H transition studies benefit from high spatial temporal resolution measurements pedestal profile evolution (temperature, density radial electric field) stability edge current has been inferred motional Stark effect measurements. The...
The structure of currents and electric fields in the edge tokamak plasma is analysed for detached regimes a tokamak. Strong divertor regions near X‐point are typical regimes. It shown that value poloidal field with temperature 1–2 eV determined by Spitzer conductivity parallel currents. latter combination thermal Pfirsch–Schlüter (PS) E × B drifts have significant impact on distribution divertor. Stability strong also analysed. has been demonstrated so‐called PS instability caused current...
Abstract SOLPS-ITER modelling databases of three tokamaks—ASDEX-Upgrade, JET and ITER with fluid drifts activated are compared to understand the dependence edge plasma performance on machine size other global parameters. Two medium Z extrinsic radiating impurity species (Ne N) considered. It is demonstrated that N better kept in divertor region than Ne semi-detached detached conditions due smaller first ionization potential (FIP effect). Together fact radiates more efficiently at higher...
Abstract The two-dimensional edge plasma code SOLPS-ITER have been used to study the hydrogen isotope effect on divertor detachment onset for (H), deuterium (D), and tritium (T) based EAST conditions. Results prove that H with a lighter mass has stronger ability penetrate into core than D T, resulting in higher density lower SOL. If line-averaged electron is selected characterize onset, strongly dependent measurement chord location which determines contribution of density. modeling results...
Abstract In the paper a SOLPS-ITER modeling of H-Mode scenarios with different seed impurity gases (N, Ne, Ar, Kr) is performed for ASDEX Upgrade geometry. These are compared from point view their radiation efficiency and compression in divertor, which generally understood as ratio divertor to upstream density. Three seeding levels each gas considered: trace level, level sufficient radiate half incoming power so high rate that X-Point Radiator (XPR) starts form. It demonstrated Ne has lowest...