A5020097328- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Metal and Thin Film Mechanics
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Hydrogen Storage and Materials
- Laser-induced spectroscopy and plasma
- Plasma Diagnostics and Applications
- Semiconductor materials and devices
- Nuclear materials and radiation effects
- Calibration and Measurement Techniques
- Ion-surface interactions and analysis
- Analytical chemistry methods development
- Graphite, nuclear technology, radiation studies
- Advanced materials and composites
- Diamond and Carbon-based Materials Research
- Gyrotron and Vacuum Electronics Research
- Atomic and Subatomic Physics Research
- Scientific Measurement and Uncertainty Evaluation
- Fluid Dynamics and Turbulent Flows
- Radiation Effects in Electronics
Moscow Engineering Physics Institute
2016-2025
Plasma (Russia)
2025
Max Planck Institute for Plasma Physics
2014-2023
Ioffe Institute
2022
Max Planck Society
2013-2018
University of Illinois Urbana-Champaign
2016
Academician M.F. Reshetnev Information Satellite Systems (Russia)
2011
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation long-term fuel retention. The (i) limiter and (ii) divertor configurations have been studied JET-ILW (JET Be first wall W divertor), compared those former JET-C carbon-based plasma-facing (PFCs)). For configuration, gross at contact point was determined situ by spectroscopy between 4% (Ein = 35 eV) more than 100%, caused...
The erosion of tungsten (W), induced by the bombardment plasma and impurity particles, determines lifetime plasma-facing components as well impacting on performance influx W into confined region. screening divertor transport in largely content core, but source strength itself has a vital impact this process. JET tokamak experiment provides access to large set erosion-determining parameters permits detailed description closest ITER one: (i) effective sputtering yields fluxes function energy...
Erosion and deposition were studied in the JET divertor during first ITER-like wall campaign 2011 to 2012 using marker tiles. An almost complete poloidal section consisting of tiles 0, 1, 3, 4, 6, 7, 8 was studied. The data from tile surfaces completed by analysis samples remote areas inner cladding. total mass material deposited decreased a factor 4–9 compared carbon all-carbon operation before 2010. Deposits consist mainly beryllium with 5–20 at.% oxygen, respectively, small amounts Ni,...
Post-mortem studies with ion beam analysis, thermal desorption, and secondary mass spectrometry have been applied for investigating the long-term fuel retention in JET ITER-like wall components. The takes place via implantation co-deposition, highest values were found to correlate thickness of deposited impurity layers. From total amount retained D over half was detected divertor region. majority is on top surface inner divertor, whereas least measured main chamber mid-plane limiter....
Post mortem analyses of JET ITER-Like-Wall tiles and passive diagnostics have been completed after each the first two campaigns (ILW-1 ILW-2). They show that global fuel inventory is still dominated by co-deposition; hence plasma parameters sputtering processes affecting material migration influence distribution retained fuel. In particular, differences between results from may be attributed to a greater proportion pulses run with strike points in divertor corners, having about 300...
The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013–14 concentrating upper inner divertor, and outer divertor corners, lifetime issues relating to tungsten coatings carbon fibre composite tiles dust/particulate generation. results show that remains region highest deposition in JET-ILW. Variations plasma configurations between first have altered material migration corners divertor. Net is shown be beneficial sense it reduces W...
A novel design of a continuous toroidal solenoid for the small spherical tokamak MEPhIST-0 is presented. The solenoid's geometry optimized in regard to stray magnetic fields perpendicular based on Maxwell's equations and interface conditions fields. solutions obtained may theory provide level ~10−10 tested by means COMSOL modeling. observed ratio component fields, Bp/BT approximately ~0.4% at plasma center. ripple field edge δ ~ 0.8% observed. possibility breakdown with chosen configuration...
Erosion of plasma-facing materials and successive transport redeposition eroded material are crucial processes determining the lifetime components trapped tritium inventory in redeposited layers. deposition JET divertor were studied during second ITER-like wall campaign ILW-2 2013–2014 by using a poloidal row specially prepared marker tiles including tungsten bulk tile 5. The analyzed elastic backscattering with 3–4.5 MeV incident protons nuclear reaction analysis 0.8–4.5 3He ions before...
Abstract An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on most comprehensive ex situ fuel retention data set PFCs from 2015-2016 ILW3 operating period presented. The global 4.19 × 10 23 D atoms, 0.19% injected fuel. inner divertor remains region highest (46.5%). at end calculated as 7.48 22 atoms informative for accountancy, clean-up efficacy waste liability assessments. accumulation rate...
The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during operation future fusion reactor. Present work summarizes reports fuel retention divertor resulting from two first experimental campaigns Wall. deposition pattern after second campaign shows same trend as was observed campaign: highest...
Post mortem analysis shows that mid and high atomic number metallic impurities are present in deposits on JET plasma facing components with the highest amount of Ni W, therefore largest sink, being found at top inner divertor. Sources defined as "continuous" or "specific", sources arise from ongoing erosion surfaces "specific" linked specific events which decrease over time until they no longer act a source. This contribution evaluates sinks estimates sources, balance gives an indication...
The manuscript presents an overview of the erosion and deposition data in inner outer JET divertor observed during first three ITER-like wall campaigns (JET-ILW1, JET-ILW2, JET-ILW3). Erosion were studied using core samples cut out from tiles. For a similar general pattern was all campaigns: More than 60% total occurred upper region on tiles 0 1, where Be transported deposited scrape-off layer. High only tile 5. In JET-ILW2 3, together with high power fluxes at bottom 7. Additionally, peaks...
Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed both in 2013–2014 and 2011–2014 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared Ion Beam Analysis (IBA) Secondary Mass (SIMS) data. highest amount D was found on the top part inner which regions thickest deposited layers. This area resides deep scrape-off layer. Changes plasma configurations between first (2011–2012) second (2013–2014)...
An overview of the MEPhIST-0 educational and research small-scale spherical tokamak project is presented including vacuum vessel, magnetic field systems, diagnostics. In contrast to other small machines, it an advanced with D-shaped plasma equipped electron-cyclotron resonance pre-ionization system for startup ion-cyclotron heating wall conditioning. The design choices taken are discussed from perspective a primarily installation. machine simplified while remaining relevant larger devices....
Beryllium film deposition was studied with cavity samples in remote areas of the inner and outer JET divertor below tile 5 during 2011–2012 campaign ITER-like wall. Predominantly beryllium films were formed inside cavities some additional carbon, ratio Be/C >2. These deposited layers had high D/(Be+C) ratios about 0.3. The formation these is mainly due to sticking beryllium-containing particles low coefficients <0.5. observed surface loss probabilities depend on position divertor....