Z.M. Xie

ORCID: 0000-0003-0308-5233
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About
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Research Areas
  • Advanced materials and composites
  • Fusion materials and technologies
  • Metal and Thin Film Mechanics
  • Nuclear Materials and Properties
  • Microstructure and mechanical properties
  • High-Temperature Coating Behaviors
  • High Entropy Alloys Studies
  • Aluminum Alloys Composites Properties
  • Advanced ceramic materials synthesis
  • Semiconductor materials and devices
  • Metal Alloys Wear and Properties
  • Additive Manufacturing Materials and Processes
  • Diamond and Carbon-based Materials Research
  • Ion-surface interactions and analysis
  • High Temperature Alloys and Creep
  • Microstructure and Mechanical Properties of Steels
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Advanced Materials Characterization Techniques
  • Graphene research and applications
  • Intermetallics and Advanced Alloy Properties
  • Nuclear Physics and Applications
  • Advancements in Battery Materials
  • MXene and MAX Phase Materials
  • Nuclear materials and radiation effects
  • Advanced Battery Materials and Technologies

University of Electronic Science and Technology of China
2024

University of Science and Technology of China
2015-2024

Institute of Solid State Physics
2015-2024

Chinese Academy of Sciences
2015-2024

Hefei Institutes of Physical Science
2022-2023

Hefei University
2019

China Southern Power Grid (China)
2017

Hunan University
2012

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...

10.1038/srep16014 article EN cc-by Scientific Reports 2015-11-04

Tungsten is considered as the most promising material for plasma facing components (PFCs) in magnetic confinement fusion devices, due to its high melting temperature, thermal conductivity, low swelling, tritium retention and sputtering yield. However, brittleness, poor machinability strength at high-temperatures of tungsten limits application. Focusing on this issue, various W alloys with enhanced mechanical properties have been developed over recent decades. Among them, W-ZrC exhibit...

10.1016/j.nme.2018.07.002 article EN cc-by Nuclear Materials and Energy 2018-07-20

W-(0.2, 0.5, 1.0)wt% ZrC alloys with a relative density above 97.5% were fabricated through the spark plasma sintering (SPS) method. The grain size of W-1.0wt% is about 2.7 μm, smaller than that pure W and 0.5)wt% ZrC. results indicated W-ZrC exhibit higher hardness at room temperature, tensile strength high lower ductile to brittle transition temperature (DBTT) W. total elongation W-0.5wt% alloy 700 °C 535 MPa 24.8%, which are respectively 59% 114% those (337 MPa, 11.6%). DBTT materials in...

10.1088/1009-0630/17/12/15 article EN Plasma Science and Technology 2015-12-01
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