A5010474532- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Ion-surface interactions and analysis
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- X-ray Spectroscopy and Fluorescence Analysis
- Laser-Plasma Interactions and Diagnostics
- Electron and X-Ray Spectroscopy Techniques
- Advanced Materials Characterization Techniques
- Superconducting Materials and Applications
- Metal and Thin Film Mechanics
- Diamond and Carbon-based Materials Research
- Laser-induced spectroscopy and plasma
- Nuclear physics research studies
- Metallurgical Processes and Thermodynamics
- Ionosphere and magnetosphere dynamics
- Advanced materials and composites
- Plasma Diagnostics and Applications
- Integrated Circuits and Semiconductor Failure Analysis
- Particle accelerators and beam dynamics
- Welding Techniques and Residual Stresses
- Cold Fusion and Nuclear Reactions
- Semiconductor materials and devices
- Solar and Space Plasma Dynamics
Max Planck Institute for Plasma Physics
2016-2025
Culham Science Centre
2011-2024
Culham Centre for Fusion Energy
2024
Max Planck Society
2012-2021
IMEC
2019
KU Leuven
2019
Max Planck Institute for Plasma Physics - Greifswald
2018
Aix-Marseille Université
2013
Max Planck Innovation
2007
Forschungszentrum Jülich
2000-2001
SIMNRA is a Microsoft Windows 95/Windows NT program with fully graphical user interface for the simulation of non-Rutherford backscattering, nuclear reaction analysis and elastic recoil detection MeV ions. About 300 different reactions cross-sections are included. can calculate any ion-target combination including incident heavy ions geometry transmission geometry. Arbitrary multi-layered foils in front detector be used. Energy loss straggling includes corrections by Chu to Bohr's theory,...
The ion-driven retention of deuterium in polycrystalline tungsten (PCW) is studied experimentally and theoretically as a function temperature, incident ion energy, fluence. Deuterium was investigated by thermodesorption spectroscopy beam analysis. peculiarities behavior PCW such (i) ion-induced defect formation at low-energy implantation (ii) higher D ions (60–200eV) compared to high-energy (3keV) high fluences are considered. effect intrinsic defects (dislocations, vacancies, grain...
Management of tritium inventory remains one the grand challenges in development fusion energy, and choice plasma-facing materials is a key factor for in-vessel retention. The Atomic Molecular Data Unit International Energy Agency organized Coordinated Research Project (CRP) on overall topic reactors during period 2001-2006. This dealt with hydrogenic retention ITER's – Be, C, W compounds (mixed materials) these elements as well removal techniques. results CRP are summarized this paper...
Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W 4+ ions to various damage levels. Deuterium was implanted by high-flux plasmas in Pilot-PSI (>10 24 m −2 s −1 ) at a surface temperature below 525 K. retention has been studied nuclear reaction analysis and thermal desorption spectroscopy. We found that deuterium is strongly enhanced the bombardment saturation occurs fluence of about 3 × 10 17 . The maximum concentration damaged region measured be 1.4 at.%. This...
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...
Following the IAEA Technical Meeting on 'Advanced Methodologies for Analysis of Materials in Energy Applications Using Ion Beam Accelerators', this paper reviews current status ion beam analysis (IBA) techniques and some aspects ion-induced radiation damage materials field relevant to fusion. Available facilities, apparatus development, future research options challenges are presented discussed. The beryllium radioactivity-containing samples from experiments JET or ITER represents not only...
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...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchange of last remaining graphite tiles to W-coated ones. The plasma start-up was performed without prior boronization. It found that large He content in plasma, resulting from DC glow discharges for conditioning, leads a confinement reduction. After change D inter-shot quickly dropped and, parallel, usual H-Mode with H factors close one achieved. initial conditioning phase, oxygen concentrations...
After completion of the tungsten coating all plasma facing components, ASDEX Upgrade has been operated without boronization for 1 1/2 experimental campaigns. This allowed study fuel retention under conditions relatively low D co-deposition with low- Z impurities as well operational space a full-tungsten device unfavourable condition high intrinsic impurity level. Restrictions in operation were caused by central accumulation combination density peaking, resulting H–L backtransitions induced...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets that exposed to plasmas at widely varying conditions.By changing only one parameter a time, the isolated effects flux, time pre-damaging on modifications studied.The sample low-flux plasma (10 20 m -2 s -1 ) is mostly smooth with few areas containing very large blisters (50 -500 µm).The samples high-flux 24 show numbers smaller (1 -10 µm) in addition even protrusions (<750 nm).The size their...
Following the first JET ITER-like wall operations a detailed in situ photographic survey of main chamber and divertor was completed. In addition, selection tiles passive diagnostics were removed from vessel made available for post mortem analysis. From results initial analysis, conclusions regarding erosion, deposition, fuel retention material transport during limiter phases have been drawn. The rate deposition on inner outer base remote corners more than an order magnitude less preceding...
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....