A5022038353- Advanced materials and composites
- Fusion materials and technologies
- Nuclear Materials and Properties
- Metal and Thin Film Mechanics
- Advanced ceramic materials synthesis
- Intermetallics and Advanced Alloy Properties
- Electrodeposition and Electroless Coatings
- Powder Metallurgy Techniques and Materials
- Nuclear materials and radiation effects
- Aluminum Alloys Composites Properties
- High-Temperature Coating Behaviors
- MXene and MAX Phase Materials
- Diamond and Carbon-based Materials Research
- Electrical Contact Performance and Analysis
- Titanium Alloys Microstructure and Properties
- Electronic Packaging and Soldering Technologies
- Advanced Image Fusion Techniques
- 3D IC and TSV technologies
- Microstructure and Mechanical Properties of Steels
- Radiation Shielding Materials Analysis
- Electrical Fault Detection and Protection
- Advanced Materials Characterization Techniques
- Nanoporous metals and alloys
- Metallurgy and Material Forming
- Nanofabrication and Lithography Techniques
Hong Kong Polytechnic University
2024
Hefei University of Technology
2015-2024
China Nonferrous Metal Mining (China)
2019-2024
Nanyang Technological University
2023
Forschungszentrum Jülich
2017-2022
Central South University
2012
A wet-chemical method combined with spark plasma sintering was used to prepare a W-Y2O3 alloy. High-temperature tensile tests and nano-indentation microhardness were characterize the mechanical properties of After He-ion irradiation, fuzz He bubbles observed on irradiated surface. The irradiation embrittlement reflected by crack indentations formed during tests. phase transformation from α-W γ-W investigated X-ray diffraction (XRD) transmission electron microscopy (TEM). Polycrystallization...
Smart tungsten-based alloys are under development as plasma-facing components for a future fusion power plant. planned to adjust their properties depending on environmental conditions: acting sputter-resistant material during plasma operation and suppressing the sublimation of radioactive tungsten oxide in case an accident New smart containing yttrium presently focus research. Thin film featuring remarkable 105-fold suppression mass increase due oxidation compared that pure at 1000 °C. Newly...
Tungsten (W) currently is the main candidate as plasma-facing armour material for first wall of future fusion reactors, like DEMO. Advantages W include a high melting point, thermal conductivity, low tritium retention, and erosion yield. However, in case an accident, air ingress into vacuum vessel can occur temperature reach 1200 K to 1450 due nuclear decay heat. In absence cooling, will remain that range several weeks. At these temperatures radioactive tungsten oxide volatilizes. Therefore,...
The severe particle, radiation and neutron environment in a future fusion power plant requires the development of advanced plasma-facing materials. At same time, highest level safety needs to be ensured. so-called loss-of-coolant accident combined with air ingress vacuum vessel represents challenge. In absence coolant temperature tungsten first wall may reach 1200 °C. such temperature, neutron-activated radioactive forms volatile oxide which can mobilized into atmosphere. Smart alloys are...
Ultra-fine tungsten carbide (WC) powder refers to WC powders with a particle size between 100 500 nm. Researchers have improved the comprehensive properties of WC-based cemented carbides by preparing ultra-fine powders. Because preparation and application nano-scale powders, ultrafine-grain excellent hardness wear resistance been successfully produced. In this paper, methods are divided into solid-phase, liquid-phase, vapor-phase according state raw materials (i.e., W or C source). The...
In future fusion reactors, tungsten is a main candidate material for the plasma facing material.To overcome brittleness of tungsten, fiber-reinforced (Wf/W) composites have been developed using powder metallurgy processes.In this study, novel type Wf/W with porous matrix has field assisted sintering technology (FAST).Compared to conventional Wf/W, avoiding fiber/matrix interface simplified production process.Initial mechanical testing showed can establish promising pseudo ductile behavior an...
In this paper the impact of steady state pure D plasma on WCrY smart alloys at ion energies 120 and 220 eV is reported. For purpose a comparison with simultaneously exposed W samples drawn. Different analysis techniques employed for pre- post-plasma sample hint significant depletion Cr enrichment lower energies. Preferential sputtering leads to enhanced volumetric loss eV. Analysis redeposited material indicated local redeposition Cr. Modelling irradiation SDTrimSP used further interpret...