A5022785353- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Ion-surface interactions and analysis
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Nuclear Physics and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Metal and Thin Film Mechanics
- Diamond and Carbon-based Materials Research
- Laser-induced spectroscopy and plasma
- Particle Dynamics in Fluid Flows
- High-pressure geophysics and materials
- Electron and X-Ray Spectroscopy Techniques
- X-ray Spectroscopy and Fluorescence Analysis
- Radiative Heat Transfer Studies
- Nuclear materials and radiation effects
- Advanced Materials Characterization Techniques
- Advanced Energy Technologies and Civil Engineering Innovations
- Cold Fusion and Nuclear Reactions
- Geotechnical and construction materials studies
- Lymphatic System and Diseases
KTH Royal Institute of Technology
2016-2025
VTT Technical Research Centre of Finland
2013-2019
Osaka University
2017
Kyushu University
2017
Culham Science Centre
2014-2017
Culham Centre for Fusion Energy
2017
Uppsala University
2007-2016
Max Planck Society
2016
Max Planck Institute for Plasma Physics
2016
Japan External Trade Organization
2015
A dedicated detector system for heavy ion elastic recoil detection analysis at the Tandem Laboratory of Uppsala University is presented. Benefits combining a time-of-flight measurement with segmented anode gas ionization chamber are demonstrated. The capability species identification improved present system, compared to that obtained when using single solid state silicon full energy signal. enables separation light elements, up Neon, based on atomic number while signals from elements such as...
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)...
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 First Mirror Test in Joint European Torus (JET) with the International Thermonuclear Experimental Reactor-like wall was performed polycrystalline molybdenum mirrors. Two major types of experiments were done. Using a reciprocating probe system main chamber, short-term exposure made during 0.3 h plasma operation 71 discharges. impact on reflectivity negligible. In long-term experiment lasting 19 13 X-point plasma, 20 Mo mirrors exposed, including four coated 1 μm-thick Rh layer. Optical...
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....
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...
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...
The experiments carried out in hydrogen at the TOMAS facility show possibility of controlling plasma parameters such as temperature and electron density a combined cyclotron resonance radio frequency (ECR+RF) discharge. A maximum up to ≈6 × 1016 m−3 35 eV are observed ECR+RF propagation RF waves under weak magnetic field is analyzed. Depending on experimental conditions, radial distribution field, there can be several cases: only slow wave propagate, simultaneously fast or propagate....
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...
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....
During the carbon wall operations of JET since 2001, an extensive post-mortem analysis programme has been carried out under Task Force Fusion Technology and a similar is underway for JET-ILW tiles removed during 2012 shutdown. The first results from ITER-like have shown that overall amount deposition on divertor remote areas reduced by more than order magnitude with respect to JET-C. In addition, obtained data indicate possible interaction between Be W such as formation mixed Be–W layers....
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...
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...
Melting is one of the major risks associated with tungsten (W) plasma-facing components (PFCs) in tokamaks like JET or ITER. These are designed such that leading edges and hence excessive plasma heat loads deposited at near normal incidence avoided. Due to high stored energies ITER discharges, shallow surface melting can occur under insufficiently mitigated disruption so-called edge localised modes—power load transients. A dedicated program was carried out study physics consequences W...
Cleaning systems of metallic first mirrors are needed in more than 20 optical diagnostic from ITER to avoid reflectivity losses. Currently, plasma sputtering is considered as one the most promising techniques remove deposits coming main wall (mainly beryllium and tungsten). This work presents results cleaning rhodium molybdenum exposed JET-ILW contaminated with typical tokamak elements (including Using radio frequency (13.56 MHz) argon or helium plasma, removal mixed layers was demonstrated...
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...
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...