A5008814842- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Ion-surface interactions and analysis
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Metal and Thin Film Mechanics
- Nuclear Physics and Applications
- Diverse Scientific and Economic Studies
- Advanced materials and composites
- Advanced Materials Characterization Techniques
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Electron and X-Ray Spectroscopy Techniques
- Muon and positron interactions and applications
- Diamond and Carbon-based Materials Research
- Advanced ceramic materials synthesis
- Integrated Circuits and Semiconductor Failure Analysis
- X-ray Spectroscopy and Fluorescence Analysis
- Hydrogen Storage and Materials
- Atomic and Molecular Physics
- Cold Fusion and Nuclear Reactions
- Welding Techniques and Residual Stresses
Max Planck Institute for Plasma Physics
2016-2025
University of Augsburg
2014-2024
Penguin Random House (United States)
2020-2024
Miele (Germany)
2020-2024
Klinikum rechts der Isar
2024
University of Hildesheim
2007-2023
Max Planck Society
2012-2021
Fraunhofer Institute for Manufacturing Engineering and Automation
2015-2021
Imerys (Germany)
2017
Culham Science Centre
2016
Interactions between the plasma and vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining choice of plasma-facing materials. A prominent issue in this is tritium inventory build-up vessel, which must be limited safety reasons. The initial material selection, i.e. beryllium (Be) on main walls, tungsten (W) divertor upper baffle dome, carbon fibre composite around strike points plates, results both from attempt to reduce optimize lifetime...
Materials facing plasmas in fusion experiments and future reactors are loaded with high fluxes (1020–1024 m−2 s−1) of H, D T fuel particles at energies ranging from a few eV to keV. In this respect, the evolution radioactive inventory first wall, permeation through armour into coolant thermo-mechanical stability after long-term exposure key parameters determining applicability wall material. Tungsten exhibits fast hydrogen diffusion, but an extremely low solubility limit. Due diffusion short...
Feedback control of the divertor power load by means nitrogen seeding has been developed into a routine operational tool in all-tungsten clad ASDEX Upgrade tokamak. For heating powers above about 12 MW, its use become inevitable to protect tungsten coating under boronized conditions. The is accompanied improved energy confinement due higher core plasma temperatures, which more than compensates negative effect dilution on neutron rate. This paper describes technical details feedback...
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 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...
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation long-term fuel retention. The (i) limiter and (ii) divertor configurations have been studied JET-ILW (JET Be first wall W divertor), compared those former JET-C carbon-based plasma-facing (PFCs)). For configuration, gross at contact point was determined situ by spectroscopy between 4% (Ein = 35 eV) more than 100%, caused...
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
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...
The use of nitrogen seeding to reduce the edge plasma temperature has recently been successfully applied in ASDEX Upgrade. While performance was significantly improved compared with other species such as Ar or Ne, questions remained interaction a tungsten first wall. In particular formation thick nitride layers reduced melting and increased physical sputtering concern. Therefore dedicated laboratory experiments have performed investigate W surfaces N plasmas. Tungsten coated Si samples were...
The migration of first wall material due to erosion, plasma transport and re-deposition is one the key challenges in current future fusion devices.To predict erosion/re-deposition patterns understand underlying principal processes, global simulation code WallDYN was developed.It couples evolution surface composition impurity transport.To benchmark model, it applied JET ITER-Like Wall experiment (JET-ILW), which mimics ITER configuration thus an ideal environment validate predictive...
Abstract Fundamental understanding of hydrogen–metal interactions is challenging due to a lack knowledge on defect production and/or evolution upon hydrogen ingression, especially for metals undergoing irradiation with ion energy below the displacement thresholds reported in literature. Here, applying novel low-energy argon-sputter depth profiling method significantly improved resolution tungsten (W) surfaces exposed deuterium (D) plasma at 300 K, we show existence 10 nm thick...
The increasing importance of automation and smart capabilities for factories other industrial systems has led to the concept Industry 4.0 (I4.0). This aims at creating that improve vertical horizontal integration production through (i) comprehensive intelligent processes, (ii) informed decentralized real-time decision making, (iii) stringent quality requirements can be monitored any time. I4.0 infrastructure, supported in many cases by robots, sensors, algorithms, demands highly skilled...
Different mechanisms contribute to tritium retention in ITER, amongst which co-deposition with materials from the plasma-facing components is one of main contributors. A systematic study influence deposition conditions (substrate temperature, rate, energy incident particles) on deuterium co-deposited beryllium layers has been carried out PISCES-B. The mechanism by co-deposits appears be a combination and implantation, decreased for increased rate an particle energy. scaling equation...
The levels of retention in codeposited layers each the three ITER materials (C, Be and W) are compared. Scaling laws, based on conditions during codeposition process (surface temperature, incident particle energy ratio depositing fluxes), presented to allow prediction expected under conditions. Retention carbon codeposits scales inversely with energy, whereas metallic level proportionally increasing energy. differing scaling provides insights into which material may impact global depending...
Common diffusion trapping models for modeling hydrogen transport in metals are limited to traps with single de-trapping energies and a saturation occupancy of one. While they successful predicting typical mono isotopic ion implantation thermal degassing experiments, fail at describing recent experiments on isotope exchange low temperatures. This paper presents new modified model fill level dependent that can also explain these experiments. Density function theory (DFT) calculations predict...