A5005983150- Metal and Thin Film Mechanics
- Fusion materials and technologies
- Diamond and Carbon-based Materials Research
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Ion-surface interactions and analysis
- Advanced materials and composites
- Plasma Applications and Diagnostics
- Laser-induced spectroscopy and plasma
- Magnetic properties of thin films
- Nuclear reactor physics and engineering
- Copper Interconnects and Reliability
- Lubricants and Their Additives
- High-Temperature Coating Behaviors
- Semiconductor materials and devices
- Superconducting Materials and Applications
- Vacuum and Plasma Arcs
- Electrohydrodynamics and Fluid Dynamics
- Tribology and Wear Analysis
- ZnO doping and properties
- Silicon Carbide Semiconductor Technologies
- Dust and Plasma Wave Phenomena
- High-pressure geophysics and materials
- Ionosphere and magnetosphere dynamics
National Institute for Laser Plasma and Radiation Physics
2015-2024
Royal Military Academy
2020
Horia Hulubei National Institute for R and D in Physics and Nuclear Engineering
2017
Institutul de Fizică Atomică
2017
Science et Ingénierie des Matériaux et Procédés
2017
University of Tartu
2013
VTT Technical Research Centre of Finland
2013
KTH Royal Institute of Technology
2013
Yahoo (United Kingdom)
2010
National Research and Development Institute on Occupational Safety
2007
Work is in progress to completely replace, 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent ITER design. The ITER-like wall (ILW) will be created combination beryllium (Be), tungsten (W), W-coated and Be-coated inconel tiles, material depending on local anticipated heat flux geometry. It part an integrated package enhancements whose aim develop understanding issues techniques required operate inductive advanced scenarios as close possible...
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...
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce risks of potential release during accidents, inventory being set at 1 kg. Simulations and extrapolations from existing experiments indicate that T-retention in will mainly be driven by co-deposition with beryllium (Be) eroded first wall, co-deposits forming divertor region but also possibly on wall itself. A pulsed Laser-Induced Desorption (LID) system, called Tritium Monitor, is designed locally...
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...
Preparatory study for the operation of JET tokamak with a full metal wall (ITER-like project) also comprises several activities aiming at development thin beryllium coatings. The purpose is 2-fold: (i) to coat Inconel® tiles inner cladding; (ii) develop methods production films so-called marker in order enable monitoring Be erosion from limiters. Properties film must match, as closely possible, those bulk Be. first step R&D process was assess coating and quality layers deposited on test...
The ablation and fuel-retention characteristics of aluminum–tungsten (AlW) beryllium–tungsten (BeW) samples have been determined using Laser Induced Breakdown Spectroscopy (LIBS) compared to results obtained Secondary Ion Mass Spectrometry (SIMS). measurements made both at vacuum (of the order 10−4 Pa) 50 Pa argon especially enhance intensities spectral lines H D. For reliable evaluation rate electron density ne temperature Te LIBS plasma with help selected Be, Al, W. has from Stark...
A remote LIBS system is being considered as an analysis tool in ITER for monitoring the erosion and fuel retention first wall. This necessitates further investigation of performance thick co-deposited layers consisting ITER-relevant materials. The main goal this work determining content samples D depth profile by to compare results with those obtained other methods. studied were Be-based mixed coatings on W substrates, containing some cases C, O, or both. These impurities are relevant not...
Abstract In ITER, a remote handling laser-induced breakdown spectroscopy (LIBS) system is considered to be able observe regions where deposition of thick layers expected occur and assess the retention fuel on wall structures. The H D contents surface divertor first-wall materials have been intensely studied by LIBS but mostly depth profile analysis D. As far as we know, quantitative H/D in BeW mixed layer calibration free-LIBS (CF-LIBS) has not performed. Thus, aim this work quantification...
Since 2011 the JET tokamak has been operated with a metal ITER-like wall (JET-ILW) including castellated beryllium limiters and lamellae-type bulk tungsten tiles in divertor.This allowed for large scale test of plasma-facing components (PFC).Procedures sectioning into single blocks castellation have developed.This facilitated morphology studies surfaces inside grooves after experimental campaigns 2011-2012 2013-2014.The deposition 0.4-0.5 mm wide is 'shallow'.It reaches 1-2 12 deep...
The chosen materials for plasma facing components the deuterium/tritium phase of ITER are beryllium and tungsten. These have already been widely investigated in various devices like ion beam or electron tests. However, operation this material combination a large tokamak including wall interaction, degradation, erosion mixing has not proven yet.The ITER-like Wall, which recently installed JET, consists bulk tungsten coated CFC divertor tiles as well INCONEL main chamber. experiments JET will...
JET components are removed periodically for surface analysis to assess material migration and fuel retention. This paper describes issues related handling procedures preparing samples analysis; in particular a newly developed procedure cutting beryllium tiles is presented. Consideration also given the hazards likely due increased tritium inventory activation from 14 MeV neutrons following planned TT DT operations (DTE2) 2017. Conclusions drawn as feasibility of post DTE2.
For the ITER-like wall project at JET present main chamber CFC tiles will be exchanged with Be and in parallel a fully tungsten-clad divertor prepared. Therefore three R&D programmes were initiated: coatings on Inconel as well erosion markers developed for first of chamber. High heat flux screening cyclic loading tests carried out showed excellent performance, above required power energy density. conceptual design bulk W horizontal target plate was investigated, emphasis minimizing...
Laser-induced breakdown spectroscopy (LIBS) experiments on different ITER-relevant beryllium–tungsten mixtures were performed to develop LIBS for tokamak applications. Some of the samples doped or implanted with deuterium simulate fuel retention. The results indicate that beryllium and tungsten have a number distinguishable spectral lines diagnostics purposes, but detection is challenged by its low concentration fluences used. By studying depth profiles coatings, removal rates layers...