A5059604456- Fusion materials and technologies
- Nuclear Materials and Properties
- Metal and Thin Film Mechanics
- Ion-surface interactions and analysis
- Advanced Materials Characterization Techniques
- Aluminum Alloys Composites Properties
- Advanced materials and composites
- Metal Alloys Wear and Properties
- Metallurgy and Material Forming
- Crystallization and Solubility Studies
- Aluminum Alloy Microstructure Properties
- X-ray Diffraction in Crystallography
- Plasma Diagnostics and Applications
- Microstructure and mechanical properties
- Nuclear Physics and Applications
- Diamond and Carbon-based Materials Research
- Magnesium Alloys: Properties and Applications
- Semiconductor materials and devices
- Magnetic confinement fusion research
- Microstructure and Mechanical Properties of Steels
- High Temperature Alloys and Creep
- Metallurgical and Alloy Processes
- Muon and positron interactions and applications
- Hydrogen embrittlement and corrosion behaviors in metals
- Fatigue and fracture mechanics
Max Planck Institute for Plasma Physics
2014-2024
Forschungszentrum Jülich
2021-2024
Yan'an University
2022
Max Planck Society
2013-2021
Shanghai Jiao Tong University
2007-2016
Institute of Plasma Physics
2014-2015
Chinese Academy of Sciences
2014-2015
Hebei Agricultural University
2012-2013
China National Heavy Machinery Research Institute Co., Ltd.
2012
Sinomach (China)
2012
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 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...
Nitrogen puffing is routinely applied in nuclear fusion plasma experiments with tungsten walls to control the amount of power emitted from by radiation. However, as nitrogen retained significant amounts it adds some complexity plasma-wall interaction. Basic questions concerning interaction tungsten, namely energy and temperature dependent retention implanted into erosion formed nitride deuterium, are still open. To address these questions, laboratory a mass-filtered ion source sample...
Blistering of tungsten (W) surfaces due to deuterium (D) implantation was investigated by a sequence exposures at two different temperatures—230 and 450 K—and the reversed sequence. A single exposure 230 K leads high areal density small dome-shaped blisters (up 3 µm in diameter) together with much smaller flat-topped structures, while 450-K produces large up 40 diameter without structures. Most from disappeared after annealing for 17 h, but survived even grew size if surface exposed D plasma...
In recent years reduced activation ferritic martensitic steel has been proposed as the plasma-facing material in remote regions of first wall. This study reports erosion and deuterium retention behaviours CLF-1 exposed to (D) plasma a linear experimental system function incident ion energy fluence. The D ranges from 30 180 eV at flux 4 × 1021 m−2 s−1 up fluence 1025 m−2. SEM images revealed clear change surface morphology functions impinging energy. mass loss results showed decrease total...
Abstract Magnetron-sputtered tungsten nitride (WN x ) films were used as a model system to study the behaviour of re-deposited WN layers which could form in fusion devices with (W) wall during nitrogen seeding. The interaction such deuterium (D) plasmas was investigated dedicated laboratory experiments. D retention and N removal due plasma exposure (D flux: 9.9 × 10 19 m −2 s −1 , ion energy 215 eV) at different temperatures measured beam analysis (IBA). Low-energy argon sputtering followed...
Deuterium retention in tungsten films deposited on polycrystalline bulk substrates was investigated and compared with deuterium W silicon alone. The structure of the by x-ray diffraction scanning electron microscopy combined focused ion beam cutting. D after implantation measured nuclear reaction analysis temperature programmed desorption (TPD). show a typical columnar epitaxial growth. After implantation, high densities blisters diameters about hundred μm were formed. Interestingly, are...
Up to now, analyzing the production of dislocation-type defects in subsurface region plasma or ion-exposed tungsten samples has been hampered by challenging suitable cross-section for transmission electron microscopy. We present two reliable methods based on precision electropolishing prepare cross-sections that allow direct imaging scanning as well Using these methods, we are able demonstrate a clear enhancement dislocation density caps blisters exposed H isotope plasma, i.e., surface...
The influence of nitrogen (N) pre-implantation on the deuterium (D) retention in tungsten (W) at different temperatures was investigated.Bulk W samples were exposed to D plasma with a fluence 110 24 D/m 2 or without 300 K and 500 K, respectively.Nuclear reaction analysis applied for determination N content near surface.Optical microscopy used investigate surface modification by blistering after implantation.It is shown that, W:N layers formed during preimplantation play very roles...
Hydrogen-induced cracking (HiC) or blistering is a commonly observed feature in plasma-loaded material surfaces. HiC exhibits strong dependence on the irradiation parameters, such as incident flux and fluence, particle energy, sample temperature. However, underlying physics of this process still not understood. Focusing with intragranular cavities tungsten (W) exposed to deuterium (D) plasma, we apply one-dimensional (1D) flux-balance model further propose crucial role solute D distribution...
It is currently a challenge to accurately predict the deformation and fracture behavior of metal parts in automobile crashes. Many studies have shown that materials are significantly affected by stress state during crashes with complex characteristics. In order further promote application die-cast magnesium alloys automobiles, it particularly important study material alloys. this paper, mechanical properties AM60B alloy sheet under four states (shear, tension, R10 notch cupping) were...
316LN is a type of austenitic stainless steel whose grain refinement only depends on hot deformation. The true stress–strain curves were obtained by means compression experiments conducted at temperature range 900–1200°C and strain rate 0·001–10 s −1 . influence deformation parameters the microstructure was analysed. Both constitutive equation for model size after dynamic recrystallisation established, effect different conditions results show that suitable working region one with relatively...
Pure and Y2O3-doped tungsten samples were simultaneously exposed to deuterium (D) plasma. The following exposure parameters investigated: ion energy of 38 eV/D, sample temperatures 370, 450 570 K, incident fluences 6 × 1024 7.5 1025 D/m2. retention behavior these materials was investigated by nuclear reaction analysis thermal desorption spectroscopy. After at K shows a D depth profile comparable with that pure tungsten. But each condition higher total inventory than This is attributed the...
A method is developed for measuring the electron density in argon during atmospheric pressure dielectric barrier discharge. The oscillating electromagnetic signal detected by an antenna at a distance from plasma source. then calculated ion oscillation frequency. results show that after turnoff of discharge channel 2.55×1019 m−3 with applied voltage 2.73 kV, and it decays almost exponentially down to 1.00×1019 over 49.2 ns. found increase linearly increasing voltage.
Abstract Tungsten fiber-reinforced tungsten (W f /W) has been developed to improve the fracture toughness of W materials, as demonstrated in previous studies (2019 Nucl . Fusion 59 086034; 2021 Mater Sci Eng A 817 141361). In present study, we focus on performance /W materials under fusion-relevant test conditions and further demonstrate their use plasma facing future fusion reactors. Specifically, one set samples was exposed Ne investigate erosion resistance against sputtering, comparison...