A5078939678- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Laser-induced spectroscopy and plasma
- Ion-surface interactions and analysis
- Microstructure and mechanical properties
- Nuclear materials and radiation effects
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Hydrogen embrittlement and corrosion behaviors in metals
- Hydrogen Storage and Materials
- Ionosphere and magnetosphere dynamics
- High-Temperature Coating Behaviors
- Muon and positron interactions and applications
- Diamond and Carbon-based Materials Research
- Microstructure and Mechanical Properties of Steels
- Metallurgical Processes and Thermodynamics
- Metal Alloys Wear and Properties
- Metallurgical and Alloy Processes
- Advanced ceramic materials synthesis
Minzu University of China
2025
China University of Geosciences
2025
Chinese Academy of Sciences
2015-2024
Hefei Institutes of Physical Science
2013-2024
Institute of Plasma Physics
2015-2024
University of Science and Technology of China
2015-2024
First People's Hospital of Chongqing
2024
Anhui University
2022
Hefei National Center for Physical Sciences at Nanoscale
2013-2017
Max Planck Institute for Plasma Physics
2017
We reveal the microscopic vacancy trapping mechanism for H bubble formation in W based on first-principles calculations of energetics H-vacancy interaction and kinetics segregation. Vacancy provides an isosurface optimal charge density that induces collective binding its internal surface, a prerequisite ${\text{H}}_{2}$ molecule nucleation inside vacancy. The critical surface before is found to be ${10}^{19}--{10}^{20}\text{ }\text{H}$ atoms per ${\text{m}}^{2}$. believe such generally...
Abstract The refractory tungsten alloys with high ductility/strength/plasticity are highly desirable for a wide range of critical applications. Here we report an interface design strategy that achieves 8.5 mm thick W-0.5 wt. %ZrC alloy plates flexural strength 2.5 GPa and strain 3% at room temperature (RT) ductile-to-brittle transition about 100 °C. tensile is 991 MPa RT 582 500 °C, as well total elongation 1.1% large 41% respectively. In addition, the W-ZrC plate can sustain 3.3 MJ/m 2...
We have investigated the dissolution, segregation and diffusion of hydrogen (H) in a tungsten (W) grain boundary (GB) using first-principles method order to understand GB trapping mechanism H. Optimal charge density plays an essential role such mechanism. Dissolution H are directly associated with optimal density, which can be reflected by solution energy sequence for different interstitial sites. To occupy optimal-charge-density site, easily trapped W −0.23 eV −1.11 eV, respectively....
We investigate the physical origin of H–He interaction in W terms optimal charge density by calculating energetics and diffusion properties using a first-principles method. On one hand, we show strong attraction between H He originated from redistribution due to presence He, driving segregation towards He. This can block permeation into deeper bulk thus suppress blistering. other demonstrate that rather than H, energetically prefers occupy vacancy centre its closed-shell structure, which 2...
The EAST research program aims to demonstrate steady-state long-pulse advanced high-performance H-mode operations with ITER-like poloidal configuration and RF-dominated heating schemes. Since the 2014 IAEA FEC, has been upgraded all ITER-relevant auxiliary current drive systems, enabling investigation of plasma profile control by coupling/integration various combinations. Fully non-inductive (H 98,y2 > 1.1) was extended over 60 s for first time sole RF plus good power coupling impurity...
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...
In order to withstand rapid increase in particle and power impact onto the divertor demonstrate feasibility of ITER design under long pulse operation, upper EAST tokamak has been upgraded actively water-cooled, ITER-like tungsten mono-block structure since 2014 campaign, which is first attempt for on devices. Therefore, a new Langmuir probe diagnostic system (DivLP) was designed successfully obtain plasma parameters region such as electron temperature, density, heat fluxes. More...
The first EAST (Experimental Advanced Superconducting Tokamak) plasma ignited in 2006 with non-actively cooled steel plates as the plasma-facing materials and components (PFMCs) which were then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks 2008. wall was changed further molybdenum alloy 2012, while keeping for both upper lower divertors. With rapid increase heating current driving power EAST, W/Cu divertor project launched around end of aiming at achieving...
First-principles calculations are performed to investigate the dissolving, trapping and detrapping of H in six bcc (V, Nb, Ta, Cr, Mo, W) fcc (Ni, Pd, Pt, Cu, Ag, Au) metals. We find that zero-point vibrations do not change site-preference order at interstitial sites these metals except Pt. One vacancy could trap a maximum 4 atoms Au 6 V, Ni, Cu 12 Mo W. The never number trapped single By calculating formation energy vacancy-H (Vac-Hn) complex, superabundant Pd Ni is demonstrated be much...
The behaviours of hydrogen and helium in tungsten are vitally important fusion research because they can result the degradation material. In present work, we carry out density-functional theory calculations to investigate clustering atoms at interstitial sites, vacancy small clusters (Vacm, m = 2, 3), influence on evolution tungsten. We find that extremely difficult aggregate sites form a stable cluster However, energetically favourable together close-packed arrangement between (1 1 0)...
Radiation-induced damage in tungsten (W) and W alloys has been considered as one of the most important issues fusion research, because radiation-produced defects not only degrade mechanical property but also change behaviours H He significantly, such retention H. Nano-structured developed to reduce accumulation within grains further mitigate radiation-induced damage. However, fundamental role a grain boundary (GB) healing radiation is yet well understood. Using molecular dynamics statics, we...