T. Wauters
A5002843357- Magnetic confinement fusion research
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Atomic and Molecular Physics
- Nuclear Physics and Applications
- Advanced Radiotherapy Techniques
- Laser-induced spectroscopy and plasma
- Solar and Space Plasma Dynamics
- Electrostatic Discharge in Electronics
- High voltage insulation and dielectric phenomena
- Medical Imaging Techniques and Applications
- Astronomical Observations and Instrumentation
- Astronomy and Astrophysical Research
- Radiation Therapy and Dosimetry
- Silicon Carbide Semiconductor Technologies
- Spacecraft and Cryogenic Technologies
- Particle Accelerators and Free-Electron Lasers
- Dust and Plasma Wave Phenomena
- Material Properties and Failure Mechanisms
ITER
2022-2025
Kharkiv Institute of Physics and Technology
2023
Royal Military Academy
2014-2021
National Centre for Nuclear Research
2021
Forschungszentrum Jülich
2011-2021
Princeton Plasma Physics Laboratory
2021
HUN-REN Centre for Energy Research
2021
Laboratoire de Physique des Plasmas
2013-2020
Plasma (Russia)
2015
CEA Cadarache
2009-2013
After completing the main construction phase of Wendelstein 7-X (W7-X) and successfully commissioning device, first plasma operation started at end 2015. Integral start-up using electron cyclotron resonance heating (ECRH) an extensive set diagnostics have been completed, allowing initial physics studies during operational campaign. Both in helium hydrogen, breakdown was easily achieved. Gaining experience with vessel conditioning, discharge lengths could be extended gradually. Eventually,...
The optimized, superconducting stellarator Wendelstein 7-X went into operation and delivered first measurement data after 15 years of construction one year commissioning. Errors in the magnet assembly were confirmend to be small. Plasma was started with 5 MW electron cyclotron resonance heating (ECRH) power five inboard limiters. Core plasma values keV, keV at line-integrated densities achieved, exceeding original expectations by about a factor two. Indications for core-electron-root found....
Wendelstein 7-X is the first comprehensively optimized stellarator aiming at good confinement with plasma parameters relevant to a future power plant. Plasma operation started in 2015 using limiter configuration. After installing an uncooled magnetic island divertor, extending energy limit from 4 80 MJ, continued 2017. For this phase, electron cyclotron resonance heating (ECRH) capability was extended 7 MW, and hydrogen pellet injection implemented. The enhancements resulted highest triple...
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...
Abstract After the second Deuterium–Tritium Campaign (DTE2) in JET tokamak with ITER-Like Wall (ILW) and full tritium campaigns that preceded followed after DTE2, a sequence of fuel recovery methods was applied to promote removal from wall components. The started several days baking main chamber walls at 240 °C 320 °C. Subsequently, superimposed Ion-Cyclotron Conditioning (ICWC) Glow Discharge (GDC) cleaning cycles deuterium. Diverted plasma operation deuterium different strike point...
In this work, the slow wave equation for Ez component and expression Poyting vector were obtained from system of Maxwell's equations. The analysis these equations is given with respect lower hybrid resonance point presence. capacities penalty method analytical continuation are analyzed in connection to their usage electromagnetic plasma propagation numerical treatment using Galerkin approach within finite element discretization. Numerical calculations carried out, values relative errors...
Plasma production in stellarators with ion cyclotron heating is complementary to the widely used electron (ECRH). The prospective light minority scenario developed and tried on Uragan-2M Large Helical Device (LHD) had been reexamined at LHD. distinctive feature of this attempt that parameters plasma produced are better than before comparable those by ECRH. This new possibility heating, if it becomes practical, motivates rethinking role stellarator machines.
The Wendelstein 7-X (W7-X) optimized stellarator fusion experiment, which went into operation in 2015, has been operating since 2017 with an un-cooled modular graphite divertor. This allowed first divertor physics studies to be performed at pulse energies up 80 MJ, as opposed 4 MJ the phase, where five inboard limiters were installed instead of a This, and number other upgrades device capabilities, extension regimes higher plasma density, heating power, performance overall, e.g. setting new...
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...
Pulsed injections of boron carbide granules into Wendelstein 7-X stellarator (W7-X) plasmas transiently increase the plasma stored energy and core ion temperatures above reference W7-X experimental programs by up to 30%. In a series 4 MW electron cyclotron resonance heating experiments, PPPL Probe Mounted Powder Injector provided 50 ms bursts 100 μm every 350 at estimated quantities ranging from approximately 1 mg/pulse over 30 mg/pulse. For each injection, was observed initially drop...
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 The full W environment that is now foreseen for ITER puts strong emphasis on experimental results obtained in present devices similar conditions. In this context, the WEST tokamak well equipped to bring key contributions preparation of operation, thanks its capability perform long pulses dominant electron heating, torque-free scheme based RF systems, and ITERgrade actively cooled divertor. Recent interest cover understanding tungsten contamination evaluation conditioning methods,...
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 Experiments have been performed under the coordination of International Tokamak Physics Activity (ITPA) on several tokamaks, including ASDEX Upgrade (AUG), JET and DIII-D, to characterize increased Ion cyclotron range frequency (ICRF) antenna loading achieved by optimizing position gas injection relative RF antennas. On AUG (with ITER-Like Wall) a 50% increase in was observed when injecting deuterium ELMy H-mode plasmas using mid-plane inlets close powered antennas instead divertor...
The low-Z oxygen and carbon were the main plasma impurities in Wendelstein 7-X (W7-X) stellarator last experimental campaign with passively cooled graphite divertor. To tackle this issue boronization (Winter et al 1989 J. Nucl. Mater. 162–4 712–23) was applied, which has led to one of achievements campaign: operation at high core densities more than 1020 m−3 hydrogen fueled plasmas due reduced radiation-induced density limit.
The current status of the mechanical and electromagnetic design for ICRF antenna system W7-X is presented. Two plugins are discussed: one consisting a pair straps with pre-matching to cover first frequency band, 25–38 MHz, second two short strap triplets band around 76 MHz. This paper focusses on lower band. Power coupling reference plasma profile studied help codes TOPICA Microwave Studio that deliver scattering matrix needed optimization geometric parameters box. Radiation power spectra...
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 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...
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
ITER as a superconducting fusion machine needs efficient wall conditioning techniques for application in the presence of permanent high toroidal magnetic field (i) reducing in-vessel impurity content, (ii) controlling surface hydrogen isotopic ratio and (iii) mitigating long-term tritium inventory build-up. Encouraging results recently obtained with ion-cyclotron (ICWC) present-day tokamaks stellarators have raised ICWC to status one most promising available routine inter-pulse overnight...