Aleksandr Zinovev

ORCID: 0000-0002-1332-5125
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Advanced materials and composites
  • Microstructure and mechanical properties
  • Metal and Thin Film Mechanics
  • High-Velocity Impact and Material Behavior
  • Microstructure and Mechanical Properties of Steels
  • Mechanical stress and fatigue analysis
  • Diamond and Carbon-based Materials Research
  • Aluminum Alloys Composites Properties
  • Vibration and Dynamic Analysis
  • Nuclear reactor physics and engineering
  • Metal Alloys Wear and Properties
  • Superconducting Materials and Applications
  • High Temperature Alloys and Creep
  • Magnetic confinement fusion research
  • Surface Treatment and Residual Stress
  • Nuclear materials and radiation effects
  • Electrical Contact Performance and Analysis
  • Geotechnical Engineering and Underground Structures
  • Aluminum Alloy Microstructure Properties
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Fatigue and fracture mechanics
  • Mechanical Behavior of Composites
  • Metal Forming Simulation Techniques

Belgian Nuclear Research Centre
2016-2024

Material (Belgium)
2017-2021

UCLouvain
2017-2019

Institute of Metal Superplasticity Problems
2017-2018

Abstract The present contribution highlights results of the recent irradiation campaigns applied to screen mechanical properties advanced tungsten and copper-based materials—main candidates for application in plasma-facing components (PFC) European DEMO, which has also been presented at 28th IAEA fusion energy conference. main challenges formulated programme were linked to: (I) assessment ductile-to-brittle transition temperature newly developed tungsten-based materials; (ii) investigation...

10.1088/1741-4326/ac4062 article EN Nuclear Fusion 2021-12-07

Severe plastic deformation of tungsten (W) is known to be an efficient way reduce its inherently high ductile-to-brittle transition temperature (DBTT), what essential for use in components a fusion reactor. Thin rolled W foils possess superior mechanical behaviour at room (RT), as demonstrated previous works. It was then proposed expand the beneficial properties foil bulk by fabricating tungsten-copper (W-Cu) laminate composites, which can used structural applications. Neutron irradiation...

10.1016/j.nme.2022.101133 article EN cc-by Nuclear Materials and Energy 2022-02-10

Abstract Development of refractory metals for application as plasma-facing armour material remains among priorities fusion research programmes in Europe, China and Japan. Improving the resistance to high temperature recrystallization, enhancing strength sustain thermal fatigue cracking tolerance neutron irradiation are key indicators used down selection materials manufacturing processes be applied deliver engineering materials. In this work we investigate effect on mechanical properties...

10.1088/1741-4326/ac75fe article EN Nuclear Fusion 2022-06-06

The interaction of carbon atoms with point defects and the core edge screw dislocations Burgers vector a0/2⟨111⟩ in W a W-Re matrix is studied by means ab initio calculations. structure energetics ground-state atomic configurations are presented rationalized. It found that di-vacancies, which thermally unstable pure according to state-of-the-art calculations, can nucleate at C Re-C complexes, fill gap explanation emergence nanovoids observed experimentally under irradiation. Also, on basis...

10.1063/1.5094441 article EN Journal of Applied Physics 2019-08-19
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