Faris Sweidan

ORCID: 0000-0003-3414-8911
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About
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Research Areas
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Heat transfer and supercritical fluids
  • Advanced materials and composites
  • Metal and Thin Film Mechanics
  • Advanced ceramic materials synthesis
  • Intermetallics and Advanced Alloy Properties
  • Nuclear Engineering Thermal-Hydraulics
  • Radioactive element chemistry and processing
  • Aluminum Alloy Microstructure Properties
  • Thermal and Kinetic Analysis
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Nuclear Physics and Applications
  • Field-Flow Fractionation Techniques
  • Aluminum Alloys Composites Properties
  • Additive Manufacturing and 3D Printing Technologies
  • Fusion materials and technologies
  • Nuclear and radioactivity studies
  • Powder Metallurgy Techniques and Materials
  • High Temperature Alloys and Creep

KTH Royal Institute of Technology
2024

Jordan University of Science and Technology
2021

Korea Advanced Institute of Science and Technology
2018-2020

Functionally graded materials (FGMs) exhibit good performance owing to their gradual and directional property compositional changes occurring in the material. Field-assisted sintering is one method fabricate FGMs by utilizing a heating geometry that provides temperature gradient within sample. Here, ultra-large gradients proposed. Using finite element analyses, geometrical parameters of proposed design were optimized through systematic parametric investigation. The resulting evaluated for...

10.1016/j.matdes.2020.108714 article EN cc-by-nc-nd Materials & Design 2020-04-04

The temperature-dependent effective thermal conductivity of UN-X-UO2 (X = Mo, W) nuclear fuel composite was estimated. Following the experimental design, calculated using Finite Element Modeling (FEM), and compared with analytical models for 10%, 30%, 50%, 70% (in mass) uncoated/coated UN microspheres in a UO2 matrix. FEM results show an increase as mass fraction increases – from 1.2 to 4.6 times reference at 2000 K. agree estimated by FEM. also that Mo W coatings have similar behaviors,...

10.1016/j.jmat.2024.02.007 article EN cc-by Journal of Materiomics 2024-03-13

The irradiation resistance of tungsten (W) and a high-entropy alloy-based material W0.5(TaTiVCr)0.5 was analysed using depth marker implantation (F3+ ions irradiation). Mirror-polished W samples were exposed to 5.0 MeV 4.2 MeV, respectively, F3+ up maximum fluence 3.2x1012 ions/cm2. scanning electron atomic force microscopy implanted showed nanostructured features pinholes, whereas the surface remained fairly smooth. nanoindentation hardness increased from 6.6 GPa 8.5 13.9 16.3 GPa, due...

10.1016/j.nme.2020.100806 article EN cc-by-nc-nd Nuclear Materials and Energy 2020-10-08
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