M. Faitsch
A5042822518- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Nuclear Materials and Properties
- Solar and Space Plasma Dynamics
- Semiconductor materials and devices
- Nuclear Physics and Applications
- Advanced Algorithms and Applications
- Thermography and Photoacoustic Techniques
- High-Energy Particle Collisions Research
- Machine Learning and ELM
- Calibration and Measurement Techniques
- Gas Dynamics and Kinetic Theory
- Catalytic Processes in Materials Science
- Infrared Target Detection Methodologies
- Spacecraft and Cryogenic Technologies
- Metallurgical Processes and Thermodynamics
- Atomic and Subatomic Physics Research
- Fault Detection and Control Systems
- Electron and X-Ray Spectroscopy Techniques
Max Planck Institute for Plasma Physics
2016-2025
Culham Science Centre
2024
Culham Centre for Fusion Energy
2024
Max Planck Society
2015-2021
National Centre for Nuclear Research
2021
Royal Military Academy
2020
Max Planck Institute for Plasma Physics - Greifswald
2017
Abstract The quasi-continuous exhaust (QCE) regime is a that naturally type-I ELM-free. It combines the high density at plasma edge needed for power with normalised energy confinement typical H-mode operation. In QCE large-scale ELMs are avoided and high-frequent, low-amplitude filaments present leading to name-giving transport of particles energy.
This contribution reports first time was successfully achieved in JET metal wall. More so, it demonstrated recent deuterium-tritium...
A newly established scaling of the ELM energy fluence using dedicated data sets from JET operation with CFC & ILW plasma facing components (PFCs), ASDEX Upgrade (AUG) both and full-W PFCs MAST walls has been generated. The reveals an approximately linear dependence peak pedestal top electron pressure minor radius; a square root is seen on relative loss energy. result this gives range in parallel 10–30 MJm−2 for ITER Q= 10 2.5–7.5 intermediate at 7.5 MA 2.65 T. These latter numbers are...
published or not.The documents may come from teaching and research institutions in France abroad, public private centers.
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 The quasi-continuous exhaust (QCE) regime, formerly known as either type-II ELM or small regime is studied in ASDEX Upgrade. a natural type-I ELM-free H-mode. operational space of QCE discharges Upgrade with respect to their separatrix conditions and power capabilities are presented. A significant broadening the fall-off length observed, correlating an increased density pressure. Moreover, possible reactor relevance this demonstrated by expanding low edge safety factor demonstrating...
Abstract In future fusion reactors, extended melt pools in combination with strong plasma-induced accelerations, suggest that the metallic could reach gaps between castellated plasma-facing components, potentially accompanied by profound changes their mechanical response. The first results of a combined experimental and modelling effort to elucidate physics transport across are presented. Transient melting specially designed tungsten samples featuring toroidal has been achieved ASDEX Upgrade...
Infrared (IR) thermography is widely used in fusion research to study power exhaust and incident heat load onto the plasma facing components. Due short pulse duration of today's experiments, IR systems have mostly been designed for off-line data analysis. For future long devices (e.g., Wendelstein 7-X, ITER), a real time evaluation target temperature flux mandatory. This paper shows development capable system ASDEX Upgrade. A compact camera has incorporating necessary magnetic electric...
The search for scenarios in which tolerable power exhaust is combined with good confinement must involve high separatrix densities. We present here the first infrared thermography measurements at ASDEX Upgrade a density, H-mode regime no type-I ELMs are present. This was formerly called type-II ELM or small to distinguish it from ELMs. report on broadening of fall-off length this up factor four compared low density inter conditions. correlated an increased filament detection rate as well...
One of our grand challenges towards fusion energy is the achievement a high-performance plasma core coupled to boundary solution. The high confinement mode (H-mode) provides such due build-up an edge transport barrier leading pedestal. However, it usually features type-I localized modes (ELMs) which pose threat for long-duration operation in future devices as they induce large fluences onto facing components and typically are projected damage first wall. For devices, integration stationary...
Tokamak operational regimes with small edge localized modes (ELMs) could be a solution to the problem of large transient heat loads in fusion reactors. A ballooning mode near last closed flux surface governed by pressure gradient and magnetic shear there has been proposed for ELMs. In this Letter, we experimentally investigate several stabilizing effects present linear ideal simulations that indeed develop ballooninglike fluctuations connect them nonlinear resistive simulations. The...
We present a novel concept to tackle the power exhaust challenge of magnetically confined fusion plasma. It relies on prior establishment an X-point radiator that dissipates large fraction before it reaches divertor targets. Despite spatial proximity magnetic X point confinement region, this singularity is far away from hot plasma in coordinates and therefore allows coexistence cold dense with high potential radiate. In compact radiative (CRD) target plates are placed close point. here...
Abstract In order to extend the enhanced D-Alpha H-mode future devices, it is crucial understand properties of main signature this regime, quasicoherent mode (QCM), that likely clamps pressure gradient below ideal magnetohydrodynamic limit. The turbulent character QCM investigated with scanning probes in ASDEX Upgrade. Analysis reveals multi-faced spans both confined region (where radial electric field negative) and near scrape-off layer (SOL) positive). Fluctuations density potential at...
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...
Power exhaust is one of the major challenges for development a fusion power plant.Predictions based upon multi machine database give scrapeoff layer fall-off length λ q ≤ 1 mm large devices such as ITER.The deposition profile on target broadened in divertor by heat transport perpendicular to magnetic field lines.This broadening described spreading S. Hence both and S need be understood order estimate expected load future devices.For investigation L-Mode discharges with stable conditions...
Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...
In this work we carry out quantitative measurements of particle and heat transport associated to SOL filaments in a tokamak, relate density shoulder formation the advection energy far SOL. For first time, attempt includes direct ion electron temperatures for background filaments. With aim, combine data from number equivalent L-mode discharges ASDEX Upgrade tokamak which different probe heads were installed on midplane manipulator. This approach is validated by comparison with independent...
Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...
Abstract Negative triangularity (NT) scenarios in TCV have been compared to positive (PT) using the same plasma shapes foreseen for divertor tokamak test operations. The experiments provided a NT/PT L-mode pair and PT H-mode with different heating mixes. Regardless of mix, NT L-modes always reached higher values pressure respect power recovered central heated up twice injected power. experimental analysis shows that this enhanced performance is due larger temperature density gradients close...
Abstract A set of dedicated H-mode discharges with constant heating power combining Neutral Beam Injection and Electron Cyclotron Resonance Heating have been executed at the ASDEX Upgrade tokamak using a high triangularity magnetic geometry in order to investigate impact filamentary transport divertor non-divertor components. The evolution upstream scrape-off layer (SOL) profiles correlated separatrix quantities, mostly turbulence control parameter <mml:math...
The Alfvén instability nonlinearly excited the energetic-particle-driven geodesic acoustic mode on ASDEX-Upgrade tokamak, as demonstrated experimentally. mechanism of excitation and nonlinear evolution is not yet fully understood. In present work, a first-principles simulation using MEGA code investigated properties in both linear growth saturated phases. Here we show that successfully reproduced coexistence these two modes, agreed with experimental results well. Conclusive evidence showed...
Abstract Understanding the transport processes that determine plasma profile widths in scrape-off layer (SOL) and divertor region of tokamaks is crucial for successful power particle exhaust management future devices. Plasma from SOL into Private Flux Region (PFR) broadens profiles could mitigate challenge. Analysis ion current profiles, measured by Langmuir probes ASDEX Upgrade (AUG) tokamak, shows width PFR, normalized flux expansion between outer target midplane, about \SI{1.5}{mm} L-mode...
Abstract Electron cyclotron resonance heating (ECRH) staircase discharges in strongly shaped plasmas were performed at the full-tungsten ASDEX Upgrade tokamak to investigate enhanced Dα (EDA) H-mode, a high-confinement regime without edge localized modes (ELMs) that exhibits numerous desirable qualities for future reactors. Heating power, fueling, and plasma current scans reveal rich dynamics as traverses different confinement regimes. The L-H transition typically occurs with brief I-phase,...
Abstract We present a novel framework for quantifying radial impurity transport in the pedestal of ASDEX Upgrade (AUG) discharges. Our method is based on charge-exchange recombination spectroscopy (CXRS) measurements line radiation from multiple charge states, each along radially distributed line-of-sight array steady-state plasmas. Inverse inference diffusive-convective solver Aurora combined with synthetic diagnostic enables us to separate diffusive and convective contributions derive...