A5037371708- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Advanced Materials Characterization Techniques
- Cultural Heritage Materials Analysis
- Nuclear Physics and Applications
- Advanced ceramic materials synthesis
- Laser-induced spectroscopy and plasma
- Intermetallics and Advanced Alloy Properties
- Advancements in Materials Engineering
- Plasma Diagnostics and Applications
- Diamond and Carbon-based Materials Research
- Conservation Techniques and Studies
- High-Temperature Coating Behaviors
- Superconducting Materials and Applications
- Particle Dynamics in Fluid Flows
- Metallurgical and Alloy Processes
- Archaeological Research and Protection
- Tunneling and Rock Mechanics
- Ancient Mediterranean Archaeology and History
- Ion-surface interactions and analysis
Warsaw University of Technology
2015-2024
Royal Military Academy
2020
Institute of Plasma Physics and Laser Microfusion
2007-2014
Institute for Atomic and Molecular Physics
2013
Aristotle University of Thessaloniki
2005-2008
Sapienza University of Rome
2008
Analysis and understanding of wall erosion, material transport fuel retention are among the most important tasks for ITER future devices, since these questions determine largely lifetime availability fusion reactor. These data also extreme value to improve validate models in vessel build-up T inventory D–T devices. So far, research areas is supported by post-mortem analysis tiles. However, access samples will be very much restricted next-generation devices (such as ITER, JT-60SA, W7-X, etc)...
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
Data on erosion and melting of beryllium upper limiter tiles, so-called dump plates (DP), are presented for all three campaigns in the JET tokamak with ITER-like wall. High-resolution images wall show clear signs flash ridge roof-shaped tiles. The melt layers move poloidal direction from inboard to outboard tile, ending last DP tile an upward going waterfall-like structure. Melting was caused mainly by unmitigated plasma disruptions. During ILW campaigns, around 15% 12376 pulses were...
ITER will use beryllium as a plasma-facing material in the main chamber, covering total surface area of about 620 m2. Given importance erosion and co-deposition for tritium retention ITER, significant efforts have been made to understand behaviour under fusion-relevant conditions with high particle heat loads. This paper provides comprehensive report on state knowledge conditions: mechanisms their consequences, migration JET, fuel dust generation. The reviews basic laboratory studies,...
Abstract Results of the first dust survey in JET with ITER-Like Wall (JET-ILW) are presented. The sampling was performed using adhesive stickers from divertor tiles where greatest material deposition detected after JET-ILW campaign 2011 – 2012. emphasis especially on and analysis metal particles (Be W) aim to determine composition, size, surface topography internal structure a large set methods: high-resolution scanning transmission electron microscopy, focused ion beam, diffraction also...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after 2007 campaign by using thin W marker stripes. had full-W plasma-facing components during this campaign. The inner roof baffle net areas with a maximum about 1×1018 W-atoms cm−2 private flux region below strike point. was observed whole outer divertor, largest close to Only small fraction eroded main chamber found redeposits while large either redeposited at unidentified places or has formed dust.
Results are presented for the dust survey performed at JET after second experimental campaign with ITER-Like Wall: 2013–2014. Samples were collected on adhesive stickers from several different positions in divertor both tiles and carrier. Brittle dust-forming deposits test mirrors inner wall also studied. Comprehensive characterization accomplished by a wide range of high-resolution microscopy techniques, including focused ion beam, has led to identification classes particles: (i) beryllium...
Studying the ageing of tungsten monoblocks, their erosion and fuel inventory is priority WEST post-mortem analyses programme. Actively-cooled ITER-like plasma-facing units (PFUs) special W-coated marker lower divertor tiles were retrieved from after C3 C4 experimental campaigns to perform ex-situ analyses. The erosion/deposition pattern on was determined. deposition found mainly inner side which covered by layered deposits that increase in thickness radial direction a few hundreds nm maximum...
Abstract The Joint European Torus (JET) fusion reactor was upgraded to the metallic wall configuration in 2011 which consisted of bulk beryllium (Be) tiles main chamber and tungsten (W) W-coated CFC divertor (Matthews G.F. et al Phys. Scr. T148 014001). During each campaign, a series damages were observed; on upper dump plates (UDP) positioned top part vessel walls inner wall—mainly affecting guard limiters (IWGL). In both cases, it concluded that causes these unmitigated plasma disruptions....
Metallic mirrors will be essential components of all optical systems for plasma diagnosis in ITER. This contribution provides a comprehensive account on impact diagnostic JET with the ITER-Like Wall. Specimens from First Mirror Test and lithium-beam have been studied by spectrophotometry, ion beam analysis electron microscopy. made molybdenum were retrieved main chamber divertor after exposure to 2013–2014 experimental campaign. In chamber, only located at entrance carrier lost reflectivity...
The First Mirror Test for ITER has been carried out in JET with mirrors exposed during: (i) the third ILW campaign (ILW-3, 2015–2016, 23.33 h plasma) and (ii) all three campaigns, i.e. ILW-1 to ILW-3: 2011–2016, 63,52 total. All from main chamber wall show no significant changes of total reflectivity initial value diffuse does not exceed 3% spectral range above 500 nm. modified layer on surface very small amount impurities such as D, Be, C, N, O Ni. divertor (inner, outer, base under bulk W...
Abstract W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled test unit (TDU) made of graphite. A substantial set plasma-facing components (PFCs), including particular marker target elements, were extracted from the vessel analysed post-mortem. The analysis provided key information about underlying plasma–surface interactions (PSI) processes, namely erosion, transport, deposition as well fuel retention graphite components. net carbon (C) erosion...
Collection and ex situ studies of dust generated in controlled fusion devices during plasma operation are regularly carried out after experimental campaigns. Herewith results the survey per ...
Post-mortem and in-situ evidence is presented in favor of the generation high-velocity solid dust during explosion-like interaction runaway electrons with metallic plasma-facing components FTU. The freshly-produced source secondary de-localized wall damage through impacts that lead to formation craters, which have been reproduced dedicated light gas gun impact tests. This novel mechanism, potential importance for ITER DEMO, further supported by surface analysis, multiple theoretical...
Metal artworks are subjected to corrosion and oxidation processes due reactive agents present in the air, water ground that these objects have been contact with for hundreds of years. This is case archaeological metals recovered from excavation sites, as well artefacts exposed polluted air. Stabilization conservation state needs precise diagnostics accrued surface layers identification original, historical materials before further protective treatments, including safe laser cleaning unwanted...
Abstract Mirror tests for ITER have been carried out in JET over 15 years. During the third campaign with ITER-like wall (2015–2016), comprising a total tokamak plasma exposure duration of 23.4 h and 1027 glow discharge cleaning, new experiment was performed specially designed test assembly housing six polycrystalline molybdenum mirror samples featuring trapezoidal entrance apertures simulating geometry cut-outs diagnostic first shielding blanket. The installed on vacuum vessel at outer...