A5072826013- Fusion materials and technologies
- Advanced materials and composites
- Nuclear Materials and Properties
- Metal and Thin Film Mechanics
- Corrosion Behavior and Inhibition
- Statistical Methods and Inference
- Magnetic confinement fusion research
- Advanced Materials Characterization Techniques
- Hydrogen embrittlement and corrosion behaviors in metals
- Statistical Methods and Bayesian Inference
- Nuclear reactor physics and engineering
- Metallurgical and Alloy Processes
- Microstructure and mechanical properties
- Superconducting Materials and Applications
- Diverse Musicological Studies
- Laser-Plasma Interactions and Diagnostics
- Synthesis and Biological Evaluation
- High Temperature Alloys and Creep
- Click Chemistry and Applications
- Electrodeposition and Electroless Coatings
- Synthesis and biological activity
- Metallic Glasses and Amorphous Alloys
- Intermetallics and Advanced Alloy Properties
- Nuclear Engineering Thermal-Hydraulics
- Titanium Alloys Microstructure and Properties
Southwestern Institute of Physics
2016-2024
Ocean University of China
2024
Guangzhou University
2024
Jilin University
2019-2023
Changchun University of Technology
2014
Kookmin University
2014
China North Industries Group Corporation (China)
2010
Guizhou Institute of Technology
2008
Tungsten (W) stands out as a highly promising plasma-facing materials (PFMs) for future nuclear fusion reactors due to its advantages of excellent high temperature strength, low tritium retention and recrystallization (RCT). Notably, the potassium-doped tungsten-rhenium (W-Re-K) alloy exhibits exceptional performance when compared other potential W-based alloys. Nevertheless, even small amount Re addition can reduce thermal conductivity W, which falls short requirement PFMs. In this study,...
The effects of the addition Y2O3 and hot-deformation on mechanical properties tungsten (W) have been studied. processing route comprises a doping technique for distribution particles in matrix, conventional sintering hydrogen environment, high-energy-rate forging (HERF). microstructure composite was characterized by using transmission electron microscopy backscattering diffraction imaging technique, its were studied means tensile testing. thermal shock response HERF processed W-Y2O3...
Fine-grain tungsten alloys could be one of the solutions for plasma facing materials future DEMO reactors. In order to evaluate service performances newly developed W under edge irradiation and synergetic effect fusion together with high heat flux, both low energy He ions H, H/He mixed neutral beam on W-ZrC, W-K, W-Y2O3, W-La2O3 CVD-W coating were performed respectively at a liner facility (Dalian Nationality University, China) GLADIS (IPP, Germany). Surface damages characterized, crack...
Abstract A newly developed large-volume potassium-doped tungsten (W–K) plate with a thickness of 15 mm and weight 25 kg by powder metallurgy plus hot rolling was prepared to meet the requirements International Thermonuclear Experimental Reactor (ITER) in engineering application. In order clarify effect K doping on thermal shock performance W–K alloy, transient tests single-pulse duration 1 ms for 100 shots at room temperature were performed. The absorbed power density is set 0.33, 0.44, 0.55...
Water-cooled flat-type W/CuCrZr plasma facing components with an interlayer of oxygen-free copper (OFC) have been developed by using vacuum brazing route. The OFC layer for the accommodation thermal stresses was cast onto surface W at a temperature range 1150 °C–1200 °C in furnace. W/OFC tiles were brazed to CuCrZr heat sink 940 silver-free filler material CuMnSiCr. microstructure, bonding strength, and high flux properties joint samples investigated. W/Cu exhibits average tensile strength...
Abstract Surface damage and microscopic defect evolution of tungsten (W) armor under transient heat loads are key factors for fuel retention in fusion reactors. In this work, experiments were conducted to investigate the effects cyclic thermal shocks on deuterium (D) surface blistering W. Thermal shock recrystallized W using an electron beam with a power density 0.15 GW m −2 across 100–1500 cycles, followed by D plasma exposure high-fluence (∼1 × 10 26 ). The results demonstrate that samples...