Xiaoou Yi

ORCID: 0000-0002-5723-8058
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About
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Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Nuclear materials and radiation effects
  • Ion-surface interactions and analysis
  • Advanced materials and composites
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Microstructure and mechanical properties
  • Metal and Thin Film Mechanics
  • Radioactive element chemistry and processing
  • Advanced Materials Characterization Techniques
  • Quasicrystal Structures and Properties
  • Covalent Organic Framework Applications
  • High voltage insulation and dielectric phenomena
  • Aerosol Filtration and Electrostatic Precipitation
  • Titanium Alloys Microstructure and Properties
  • Aluminum Alloy Microstructure Properties
  • Advanced Welding Techniques Analysis
  • Semiconductor materials and interfaces
  • Fatigue and fracture mechanics
  • Nuclear Physics and Applications
  • Intermetallics and Advanced Alloy Properties
  • Chemical Synthesis and Characterization
  • Non-Destructive Testing Techniques

University of Science and Technology Beijing
2017-2024

Shandong University of Traditional Chinese Medicine
2022

University of Oxford
2012

Due to the expression of "reduced activation", severe radioactivity tantalum (Ta) after neutron irradiation in early decay years is easily neglected. In presented study, an only 0.3 dpa by fission and followed a cooling stage 305 days, RAFM steel specimen with weight 0.8 g possessed drastic 4 mSv/hour at measuring distance 20 cm. It was ascertained that high generated 182Ta. The seriously increased danger material experiments, even though original Ta addition 0.13 wt%. Similar deteriorative...

10.1016/j.nme.2023.101432 article EN cc-by-nc-nd Nuclear Materials and Energy 2023-04-10

Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder (HCCB) test blanket module (TBM), which primary option of Chinese TBM program. The characteristic microstructural change beryllium under irradiation an important factor contributing understanding degradation physical-mechanical properties material. metal was irradiated with 100 keV Ar+ ions dose 1 × 1021/m2 at room temperature. has been investigated using transmission electron microscopy (TEM). After...

10.1016/j.nme.2017.04.009 article EN cc-by-nc-nd Nuclear Materials and Energy 2017-04-29

γ-Al2O3/FeAl coatings for tritium permeation barrier (TPB) application in fusion reactors were fabricated via electro-chemical deposition and selective oxidation. The TPB consisted of a γ-Al2O3 scale (200 nm), an upper interlayer FeAl (20 μm) lower Fe3Al (10 μm). Their potential in-reactor performance was investigated based on 6.4 MeV Fe3+ ion irradiations at 400 °C, up to fluences 1.0 × 1019 ions·m−2 1020 ions·m−2, depth regions entailing the oxide top interlayer. Combined grazing incidence...

10.1016/j.nme.2024.101627 article EN cc-by-nc Nuclear Materials and Energy 2024-02-29

Diffusion bonding of V–4Cr–4Ti alloy to pure titanium (Ti) was carried out by hot forging in the temperature range between 1150 °C and 950 °C. The microstructure mechanical properties bonded joint were determined using light optical microscopy (OM), scanning electron (SEM), energy dispersive spectroscopy (EDS), micro-hardness measurements, shear tests. results indicate that sound dissimilar can be obtained through processes. interface has a width about 100 μm divided into two distinctive...

10.3390/app8040577 article EN cc-by Applied Sciences 2018-04-07
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