A5087260755- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Superconducting Materials and Applications
- Laser-induced spectroscopy and plasma
- Ion-surface interactions and analysis
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Metal and Thin Film Mechanics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Diamond and Carbon-based Materials Research
- Metallurgical Processes and Thermodynamics
- Analytical chemistry methods development
- X-ray Spectroscopy and Fluorescence Analysis
- Laser-Matter Interactions and Applications
- Solid State Laser Technologies
- Shape Memory Alloy Transformations
- High Entropy Alloys Studies
- Orbital Angular Momentum in Optics
- Semiconductor materials and devices
- Magnetic and transport properties of perovskites and related materials
- Advanced materials and composites
VTT Technical Research Centre of Finland
2016-2025
Fusion (United States)
2020
Fusion Academy
2020
Royal Military Academy
2020
Tekes
2010-2016
Japan External Trade Organization
2015
Culham Science Centre
2011-2014
National Institute for Laser Plasma and Radiation Physics
2011-2013
University of Tartu
2013
Institute of Engineering Physics
2013
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...
Abstract Laser-induced breakdown spectroscopy (LIBS) is one of the most promising methods for quantitative in-situ determination fuel retention in plasma-facing components (PFCs) magnetically confined fusion devices like ITER and JET. In this article, current state understanding LIBS development applications will be presented, based on a complete review existing results complemented with newly obtained data. The work has been performed as part research programme, set up EUROfusion...
Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...
Abstract Since the publication of review Progress in ITER Physics Basis (PIPB) 2007, significant progress has been made understanding processes at plasma-material interface. This review, part ITPA Nuclear Fusion Special Issue On Path to Burning Plasma Operation , presents these developments, focusing on key areas such as physics plasma exhaust, interactions, and properties plasma-facing materials their evolution under exposure. The coordinated efforts Topical Group Scrape-Off Layer Divertor...
A detailed cross-device investigation on the role of filamentary dynamics in high-density regimes has been performed within EUROfusion framework, comparing ASDEX Upgrade (AUG) and TCV tokamaks. Both devices run density ramp experiments at different levels plasma current, keeping toroidal field or q95 constant order to disentangle parallel connection length current. During scan a field, both scrape-off layer (SOL) profiles tend develop clear SOL shoulder lower edge whenever current is...
This paper summarizes the physical principles behind novel three-ion scenarios using radio frequency waves in ion cyclotron range of frequencies (ICRF). We discuss how to transform mode conversion electron heating into a new flexible ICRF technique for and fast-ion generation multi-ion species plasmas. The theoretical section provides practical recipes selecting plasma composition realize scenarios, including two equivalent possibilities choice resonant absorbers that have been identified....
Abstract The paper reports the first demonstration of in situ laser-induced desorption — quadrupole mass spectrometry (LID-QMS) application on a large scale fusion device performed summer 2023. LID-QMS allows direct measurements fuel inventory plasma facing components without retrieving them from device. diagnostic desorbs retained gases by heating 3 mm diameter spot wall using 1 ms long laser pulse and detects QMS. Thus, it can measure gas content at any position accessible to laser....
The GLAST-AGILE Support Program (GASP) of the Whole Earth Blazar Telescope (WEBT) monitored BL Lacertae in 2008-2009 at radio, near-IR, and optical frequencies. During this period, high-energy observations were performed by XMM-Newton, Swift, Fermi. We analyse these data with particular attention to calibration Swift UV data, apply a helical jet model interpret source broad-band variability. GASP-WEBT show an flare 2008 February-March, oscillations several tenths mag on few-day time scale...
The TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional heating compatible high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden operational range without sacrificing fundamental flexibility. rooted three-pronged approach aimed at ITER support, explorations towards DEMO, research. A 1 MW, tangential neutral beam injector (NBI) was recently installed promptly...
Wall conditioning is essential in tokamak and stellarator research to achieve plasma performance reproducibility. This paper presents an overview of recent results, both from experiments present devices modelling, view with superconducting coils, focus on W7-X, JT-60SA ITER. In these devices, the coils stay energised throughout experimental day or week which demands for new techniques that work presence nominal field, addition proven methods such as baking, glow discharge (GDC) low-Z wall...
Abstract ITER will operate with a tungsten divertor, material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of so called fuzz under specific conditions. Investigating interactions between plasma facing components and plasmas tokamak environment is therefore key point consolidate predictions for divertor performance lifetime. To this end, dedicated campaign was performed full WEST tokamak, cumulating ∼2000 s repetitive L mode discharges. It...
Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET's 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding control schemes. These were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure 2023. A core-edge-SOL integrated H-mode scenario developed tested D-T, showing...
Abstract This work investigates the role of surface topography in sputtering process tungsten (W) exposed to helium plasma using GyM linear device. Surfaces with varying roughness, from sub-nanometer ≅1 μm, and different textures, including random-like regular configurations, were studied. The samples at energies 30 350 eV, fluence ≅4.3e24 He + m -2 temperatures well below bulk W fuzz formation threshold ≅700 °C. interpretation experimental results was supported by simulations ERO2.0 code....
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.
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...
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...
Abstract The net erosion and deposition patterns in the inner outer divertor of WEST were determined after different experimental campaigns (C3 C4) first operational phase using ion beam analyses scanning electron microscopy techniques. performed on four entire tiles from inertially cooled, W-coated units with an additional Mo marker coating covered a further W coating. Strong occurred at expected location strike line area campaign-averaged rate >0.1 nm s −1 . On high field side area,...
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...
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...