Radiation effects on the microstructure of a 9Cr-ODS alloy

Jian Gan, T. R. Allen, R. C. Birtcher, S. Shutthanandan, S. Thevuthasan

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    7 Citations (Scopus)


    Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.

    Original languageEnglish
    Pages (from-to)24-28
    Number of pages5
    Issue number1
    Publication statusPublished - 1 Jan 2008


    ASJC Scopus subject areas

    • Materials Science(all)
    • Engineering(all)

    Cite this

    Gan, J., Allen, T. R., Birtcher, R. C., Shutthanandan, S., & Thevuthasan, S. (2008). Radiation effects on the microstructure of a 9Cr-ODS alloy. JOM, 60(1), 24-28. https://doi.org/10.1007/s11837-008-0003-5