- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Laser-induced spectroscopy and plasma
- Particle accelerators and beam dynamics
- Atomic and Molecular Physics
- Micro and Nano Robotics
- Granular flow and fluidized beds
- Microfluidic and Bio-sensing Technologies
- Particle Dynamics in Fluid Flows
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Electrostatics and Colloid Interactions
- Nuclear Materials and Properties
- Mass Spectrometry Techniques and Applications
- Fluid Dynamics and Heat Transfer
- Model Reduction and Neural Networks
- Advancements in Semiconductor Devices and Circuit Design
- Experimental and Theoretical Physics Studies
- Silicon Carbide Semiconductor Technologies
- Material Dynamics and Properties
- Viral Infections and Vectors
- Atomic and Subatomic Physics Research
Institute of Plasma Physics and Laser Microfusion
2017-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
National Centre for Nuclear Research
2021
Institute of Fundamental Technological Research
2015-2018
Polish Academy of Sciences
2015-2018
JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become widely used versatile studying large-scale plasma instabilities and their control developed in an international community. This article gives comprehensive overview of the physics models implemented, numerical methods applied solving equations studies performed with code. A dedicated section highlights some verification work done hierarchy different available...
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 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 Wendelstein 7-X (W7-X), the largest advanced stellarator, is built to demonstrate high power, performance quasi-continuous operation. Therefore, in recent campaign, experiments were performed prepare for long pulse operation, addressing three critical issues: development of stable detachment, control heat and particle exhaust, impact leading edges on plasma performance. The exhaust W7-X realized with help an island divertor, which utilizes large magnetic islands at boundary. This...
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...
For successful operation of Wendelstein 7-X (W7-X) control plasma impurity content and fuel recycling is required. This can be achieved by using wall conditioning methods. During the first divertor campaign (OP1.2a) W7-X glow discharge (GDC), weekly in hydrogen daily helium for removal respectively, was used absence magnetic field. He electron cyclotron resonance heating (ECRH) discharges were applied density plasmas during experimental days. The optimization GDC ECRH on are presented....
The paper reports on the optimization process of soft X-ray pulse height analyzer installed Wendelstein 7-X (W7-X) stellarator. It is a 3-channel system that records spectra in range from 0.6 to 19.6 keV. spectra, with temporal and spatial resolution 100 ms 2.5 cm (depending selected slit sizes), respectively, are line integrated along line-of-sight crosses near plasma center. In second W7-X operation phase carbon test divertor unit, light impurities, e.g., oxygen, were observed as well mid-...
Abstract Hydrodynamic interactions between two identical elastic dumbbells settling under gravity in a viscous fluid at low Reynolds number are investigated using the point-particle model. The evolution of benchmark initial configuration is studied, which vertical and their centres aligned horizontally. Rigid pairs separate beads starting from same positions tumble periodically while settling. We find that elasticity (which breaks time-reversal symmetry motion) significantly affects system...
The dynamics of regular clusters many nontouching particles falling under gravity in a viscous fluid at low Reynolds number are analyzed within the point-particle model. evolution two families particle configurations is determined: or four horizontal polygons (called "rings") centered above below each other. Two rings fall together and periodically oscillate. Four usually separate from other with chaotic scattering. For hundreds thousands initial configurations, map cluster lifetime...
In this short review, we visualize the fluid velocity generated by a point force close to plane free surface or rigid wall. We present separately contributions from all multipoles which form corresponding classical systems of images. Such graphical images might be useful in theoretical and numerical modeling dynamics micro-objects moving an interface.
The Pulse Height Analysis (PHA) system at Wendelstein 7-X (W7-X) is a broad energy range spectrometer dedicated to the observation of impurity behaviour during plasma discharges. measures spectra in between 0.5 and 20 keV, from integrated signals along three lines sight that pass close center. During recent operational phase W7-X, TESPEL (Tracer-Encapsulated Solid PELlet) injector has been commissioned. By this injector, polystyrene pellets with single tracer as well multiple impurities have...