A5052126685- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Metal and Thin Film Mechanics
- Ion-surface interactions and analysis
- Advanced materials and composites
- Diamond and Carbon-based Materials Research
- Advanced Materials Characterization Techniques
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Vacuum and Plasma Arcs
- Semiconductor materials and devices
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Electron and X-Ray Spectroscopy Techniques
- Metallurgical Processes and Thermodynamics
- Particle accelerators and beam dynamics
- High-Temperature Coating Behaviors
- Advanced Chemical Physics Studies
- Advanced ceramic materials synthesis
- High-pressure geophysics and materials
- Advanced Sensor Technologies Research
- Copper Interconnects and Reliability
Max Planck Institute for Plasma Physics
2016-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
Culham Science Centre
2024
Culham Centre for Fusion Energy
2024
Max Planck Society
2012-2021
Max Planck Institute for Plasma Physics - Greifswald
2021
Technical University of Munich
2016-2020
Royal Military Academy
2020
Forschungszentrum Jülich
1992-2016
Abstract The optimized superconducting stellarator device Wendelstein 7-X (with major radius , minor and plasma volume) restarted operation after the assembly of a graphite heat shield 10 inertially cooled island divertor modules. This paper reports on results from first high-performance operation. Glow discharge conditioning ECRH discharges in helium turned out to be important for density edge radiation control. Plasma densities with central electron temperatures were routinely achieved...
Abstract Research on magnetic confinement of high-temperature plasmas has the ultimate goal harnessing nuclear fusion for production electricity. Although tokamak 1 is leading toroidal magnetic-confinement concept, it not without shortcomings and community therefore also pursued alternative concepts such as stellarator. Unlike axisymmetric tokamaks, stellarators possess a three-dimensional (3D) field geometry. The availability this additional dimension opens up an extensive configuration...
Abstract The JET 2019–2020 scientific and technological programme exploited the results of years concerted engineering work, including ITER-like wall (ILW: Be W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power 2019–2020, tested technical procedural preparation for safe operation with tritium. Research along three complementary axes yielded wealth new results. Firstly, plasma delivered scenarios...
Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...
Abstract The most efficient and promising operational regime for the International Thermonuclear Experimental Reactor tokamak is high-confinement mode. In this regime, however, periodic relaxations of plasma edge can occur. These edge-localized modes pose a threat to integrity fusion device. Here we reveal strong impact energetic ions on spatio-temporal structure in tokamaks using nonlinear hybrid kinetic–magnetohydrodynamic simulations. A resonant interaction between fast at electromagnetic...
The tungsten programme in ASDEX Upgrade is pursued towards a full high-Z device. spectroscopic diagnostic of W has been extended and refined the cooling factor re-evaluated. coated surfaces now represent fraction 65% all plasma facing components (24.8 m2). only two major that are not yet strikepoint region lower divertor as well limiters at low field side. While extending surfaces, concentration discharge behaviour have changed gradually pointing to critical issues when operating with wall:...
The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten Copper alloys primary candidates for materials (PFMs) coolant tube materials, respectively, mainly due thermal conductivity and, in the case tungsten, its melting point. this paper, recent understandings future issues on responses tungsten Cu environments (high flux (including T He), flux, neutron doses) reviewed. This review paper includes; Tritium retention (K. Schmid M....
The formation of metallic nanostructures by exposure molybdenum and tungsten surfaces to high fluxes low energy helium ions is studied as a function the ion energy, plasma time, surface temperature. Helium leads nanoscopic filaments on both metals. size helium-induced nanostructure increases with increasing temperature while thickness modified layer time. In addition, growth rate nanostructured also depends appears linked near-surface voids induced ions. results presented here thus...
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 For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...
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...
Blistering and deuterium retention in re-crystallized tungsten exposed to low-energy, high flux pure helium-seeded D plasmas a fluence of 1027 m−2 have been examined with scanning electron microscopy, thermal desorption spectroscopy, the D(3He,p)4He nuclear reaction at 3He energies varied from 0.69 4.0 MeV. In case exposure plasma (38 eV D−1), blisters various shapes sizes depending on temperature are found W surface. No appear temperatures above 700 K. The increases temperature, reaching...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchange of last remaining graphite tiles to W-coated ones. The plasma start-up was performed without prior boronization. It found that large He content in plasma, resulting from DC glow discharges for conditioning, leads a confinement reduction. After change D inter-shot quickly dropped and, parallel, usual H-Mode with H factors close one achieved. initial conditioning phase, oxygen concentrations...
Recrystallized polycrystalline tungsten was exposed to a deuterium plasma beam with high flux (1022 D m−2 s−1) and low energy (38 eV D−1) fluences up 1027 m−2. The sample temperature varied between 320 800 K. three-dimensional morphology of blister-like structures the grain orientation were investigated by scanning electron microscopy combined focused ion cross-sectioning backscattering diffraction. Cracks distorted areas (<650 K) large cavities (100–1000 μm3) at boundaries (>480 observed...
The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets that exposed to plasmas at widely varying conditions.By changing only one parameter a time, the isolated effects flux, time pre-damaging on modifications studied.The sample low-flux plasma (10 20 m -2 s -1 ) is mostly smooth with few areas containing very large blisters (50 -500 µm).The samples high-flux 24 show numbers smaller (1 -10 µm) in addition even protrusions (<750 nm).The size their...
The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...