In situ heavy ion irradiation in ferritic/martensitic ODS steels at 500°C
Autor: | Ken He Zhang, Odile Kaitasov, Zhongwen Yao, Zhangjian Zhou, Stéphanie Jublot-Leclerc, Mark R. Daymond |
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Přispěvatelé: | Centre de Sciences Nucléaires et de Sciences de la Matière (CSNSM), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS) |
Jazyk: | angličtina |
Rok vydání: | 2017 |
Předmět: |
Materials science
Alloy Oxide Nucleation 02 engineering and technology engineering.material 01 natural sciences Ion chemistry.chemical_compound 0103 physical sciences General Materials Science Irradiation 010302 applied physics [PHYS]Physics [physics] Mechanical Engineering fungi Metallurgy technology industry and agriculture 021001 nanoscience & nanotechnology Condensed Matter Physics chemistry Mechanics of Materials Transmission electron microscopy Martensite engineering Grain boundary 0210 nano-technology |
Zdroj: | Mater.Sci.Technol. Mater.Sci.Technol., 2017, 34 (1), pp.42-46. ⟨10.1080/02670836.2017.1353660⟩ |
DOI: | 10.1080/02670836.2017.1353660⟩ |
Popis: | International audience; Three different ferritic/martensitic oxide dispersion-strengthened steels (9Cr, 12Cr and 16Cr) were irradiated using dual beam ions (Kr+ and He+), 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 interstitial loops. |
Databáze: | OpenAIRE |
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