<i>In situ</i> heavy ion irradiation in ferritic/martensitic ODS steels at 500°C

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  • Zhongwen Yao
    Department of Mechanical and Materials Engineering, Queen's University, Kingston, ON, Canada
  • Ken He Zhang
    Department of Mechanical and Materials Engineering, Queen's University, Kingston, ON, Canada
  • Zhangjian Zhou
    School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing, PR China
  • Mark R. Daymond
    Department of Mechanical and Materials Engineering, Queen's University, Kingston, ON, Canada
  • Stephanie Jublot-Leclerc
    Centre de Spectrométrie Nucléaire et de Spectrométrie de Masse (CSNSM), Univ Paris-Sud, CNRS, Université Paris Saclay, Orsay, France
  • Odile Kaitasov
    Centre de Spectrométrie Nucléaire et de Spectrométrie de Masse (CSNSM), Univ Paris-Sud, CNRS, Université Paris Saclay, Orsay, France

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<jats:p> Three different ferritic/martensitic oxide dispersion-strengthened steels (9Cr, 12Cr and 16Cr) were irradiated using dual beam ions (Kr<jats:sup>+</jats:sup> and He<jats:sup>+</jats:sup>), with in situ transmission electron microscope observation. Helium was found to be essential in cavity nucleation and growth. The 9Cr alloy presented the lowest formation of cavities among the three irradiated steels, which is attributed to the presence of significant amounts of martensite. During the irradiation of 16Cr alloy with dual beam ions, cavity segregation to grain boundaries was observed at a relatively low dose ∼1 dpa, whereas it occurred at ∼2 dpa in 9Cr and 12Cr alloys. Nano-sized Y–Ti–O particles were stable during the entire irradiation to ∼8 dpa. The lattice defects were characterised and mainly consist of [Formula: see text] interstitial loops. </jats:p>

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