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

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Abstract

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.

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Authors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, USA

    J. Gan

  2. University of Wisconsin-Madison, Madison, USA

    T. R. Allen

  3. Argonne National Laboratory, Argonne, USA

    R. C. Birtcher

  4. Pacific Northwest National Laboratory, Richland, USA

    S. Shutthanandan & S. Thevuthasan

  5. Materials and Fuels Complex, P.O. Box 1625, Idaho Falls, ID, 83415-7996, USA

    J. Gan

Authors
  1. J. Gan
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  2. T. R. Allen
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  3. R. C. Birtcher
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  4. S. Shutthanandan
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  5. S. Thevuthasan
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Correspondence to J. Gan.

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

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  • DOI: https://doi.org/10.1007/s11837-008-0003-5

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