A5091284203- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Particle accelerators and beam dynamics
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Metallurgy and Cultural Artifacts
- Model Reduction and Neural Networks
- Network Traffic and Congestion Control
- Computational Fluid Dynamics and Aerodynamics
- Microstructure and Mechanical Properties of Steels
- Meteorological Phenomena and Simulations
- Distributed systems and fault tolerance
- Vehicle emissions and performance
- Anomaly Detection Techniques and Applications
- Metallurgical Processes and Thermodynamics
- Radiative Heat Transfer Studies
- High-Energy Particle Collisions Research
- Electrostatic Discharge in Electronics
- Atomic and Molecular Physics
Universität Innsbruck
2025
Forschungszentrum Jülich
2015-2024
Culham Science Centre
2010-2024
CEA Cadarache
2024
Dutch Institute for Fundamental Energy Research
2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
Culham Centre for Fusion Energy
2013-2024
Max Planck Institute for Plasma Physics - Greifswald
2020
Royal Military Academy
2020
Max Planck Institute for Plasma Physics
2017
• Reviews the fundamental physics aspects of first ITER W divertor and defines required operational lifetime within Staged Approach. Uses SOLPS simulation database to establish target peak heat flux neutral pressure burning plasma operating domain. Assesses consequences narrow SOL channels, fluid drifts, component shaping 3D magnetic fields for ELM control. recrystallization define an budget shows that fluxes ∼50% higher than previously assumed may be acceptable. Shows Ne N should equally...
We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas edge region fusion devices. This brings together previously existing SOLPS implementations and aims become new standard version. summarize benchmarking work done ensure backward compatibility with previous work, a strong requirement on maintaining viability usability already extensive database runs used for ITER divertor design...
Operation and exploitation of present future Tokamak reactors require advanced scenario modeling in order to optimize engineering parameters the design phase as well physics performance during phase. The simulation scenarios involves simultaneous different regions reactor, characterized by symmetries, predict quantities such particle energy confinement, fusion yield, power deposited on wall, wall load from fast particles. JINTRAC is a system 25 interfaced Tokamak-physics codes for integrated...
This paper reports the impact on confinement and power load of high-shape 2.5 MA ELMy H-mode scenario at JET a change from all carbon plasma-facing components to an metal wall. In preparation this change, systematic studies reduction as result fuelling in combination with nitrogen seeding were carried out JET-C are compared their counterpart metallic An unexpected significant is reported decrease pedestal but partially recovered injection nitrogen.
Future fusion reactors require a safe, steady state divertor operation. A possible solution for the power exhaust challenge is detached operation in scenarios with high radiated fractions. The radiation can be increased by seeding impurities, such as N dominant scrape-off-layer radiation, Ne or Ar SOL and pedestal Kr core radiation. Recent experiments on two of all-metal tokamaks, ASDEX Upgrade (AUG) JET, demonstrate fractions fully-detached N, conventional vertical target geometry. For both...
The impact of carbon and beryllium/tungsten as plasma-facing components on plasma radiation, divertor power particle fluxes, neutral conditions in the divertors has been assessed JET both experimentally by edge fluid code simulations for plasmas low-confinement mode. In high-recycling studies show a 30% reduction total radiation scrape-off (SOL) layer when replacing (JET-C) with beryllium main chamber tungsten (JET-ILW). Correspondingly, at low-field side (LFS) plate two-fold increase...
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...
Using the new version of SOLPS plasma boundary code package, SOLPS-ITER, paper presents first ever simulations ITER burning baseline H-mode edge with drifts and currents activated.Neon (Ne) seeded discharges for divertor power dissipation are considered.The results scrape-off layer (SOL) parameters without compared, both SOLPS-ITER against earlier SOLPS-4.3modelling (which did not include a drift description) constituting bulk existing simulation database.Whereas effect on equatorial...
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...
Future fusion reactors require a safe, steady-state divertor operation. With deep detachment, which is typically induced by impurity seeding, the radiation concentrates in small region at X-point or on closed flux surfaces above X-point. This so-called radiator (XPR) moves further inside confined with increasing seeding and location can be actively controlled. At AUG, parameter space for operation an XPR was significantly extended, using active feedback location. The observed nearly whole...
Experiments on JET with a carbon-fibre composite wall have explored the reduction of steady-state power load in an ELMy H-mode scenario at high Greenwald fraction ∼0.8, constant and close to L H transition. This paper reports systematic study due effect fuelling combination seeding over wide range pedestal density ((4–8) × 1019 m−3) detailed documentation divertor, main plasma conditions, as well comparative two extrinsic impurity nitrogen neon. It also impact overall behaviour, possible...
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...
Abstract Results from three-dimensional modeling of plasma edge transport and plasma–wall interactions during application resonant magnetic perturbation (RMP) fields for control edge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The full 3D fluid kinetic neutral code EMC3-EIRENE is used modeling. Four characteristic perturbed topologies considered discussed with reference to axisymmetric case without RMP fields. Two field amplitudes at half ELM coil current...
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with ITER-like wall (ILW). global beryllium (Be) erosion deposition simulated compared experimental results from passive spectroscopy. For limiter configuration, it demonstrated that Be self-sputtering an important contributor (at least 35%) erosion. Taking this contribution into account, confirms previous evidence high deuterium (D) surface concentrations up ∼ 50% atomic...
Burning plasmas with 500 MW of fusion power on ITER will rely partially detached divertor operation to keep target heat loads at manageable levels. Such regimes be maintained by a real-time control system using the seeding radiative impurities like nitrogen (N), neon or argon as actuator and one more diagnostic signals sensors. Recently, detachment has been successfully achieved in Type I ELMy H-mode JET-ITER-like wall discharges saturation current (Isat) measurements from Langmuir probes...
To study the impact of strong impurity radiation on energy confinement and discharge stability at JET-ILW, dedicated high-density, highly heated experiments with neon seeding have been performed. In these an increase in core especially pedestal region plus a characteristic X-point radiator inside confined observed. The increased separatrix had no confinement. Only highest puff rates heating powers () weak H-mode without back-transitions to L-mode (M-mode) could be achieved, while lower or...
The low temperature boundary layer plasma (scrape-off or SOL) between the hot core and surrounding vessel determines level of power loading, erosion implantation material surfaces, thus viability tokamak-based fusion as an energy source. This study explores mechanisms affecting formation flattened density profiles, so-called 'density shoulders', in low-field side (LFS) SOL, which modify ion neutral fluxes to surfaces—and subsequent erosion. There is evidence against local enhancement...
Abstract The X-point radiator (XPR) is an attractive scenario that may contribute to solving the power exhaust problem in future fusion devices. 2D transport code SOLPS-ITER was applied reproduce experimentally measured plasma condition with XPR ASDEX Upgrade tokamak and compare a reduced model. Neutrals penetrating from adjoining cold divertor region large connection length near play important role initiating XPR. However, once such created, it persists even if fueling impurity seeding...
Abstract A review is given on the highlights of a scatter-shot approach developing machine-learning methods and artificial neural networks based fast predictors for application to fusion exhaust. The aim enable facilitate optimized improved modeling allowing more flexible integration physics models in light extrapolations towards future devices. project encompasses various research objectives: (a) developments surrogate model power & particle exhaust plants; (b) assessments...
Abstract A novel approach for explicitly and robustly accounting epistemic uncertainties in plasma confinement the 0-D design of tokamaks is presented, which safety factor at 95\textsuperscript{th} percentile flux surface, $q_{95}$, used to apply a margin on terms H-factor, $H$. 

The PROCESS code explore EU-DEMO space aspect ratio, major radius, net electric power, $P_{el,net}$ using above approach. comprehensive account input assumptions underlying models given. We...
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...