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    Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel

    Published: Jan 2001

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    Void swelling and radiation-induced segregation have been measured in 304 stainless steel. Samples were irradiated in the outer regions of the EBR-II reactor where displacement rates of 2.0×10-8 and 6.6 ×10-8 dpa/s are comparable to those in pressurized water reactor components. Samples were irradiated at temperatures from 371-390°C to total doses of up to 20 dpa. Void swelling reached a maximum of 2 % at 20 dpa. Nickel enrichment and chromium depletion to of 20 at% and 12 at% respectively were measured. Both void swelling and radiation-induced segregation were dependent on dose rate, increasing as the dose rate decreased. Grain boundary compositions were measured both near and in areas free of precipitates. The presence of a precipitate significantly changes the grain boundary compositions near the precipitate.


    void swelling, radiation-induced segregation, austenitic steels

    Author Information:

    Allen, TR
    Argonne National Laboratory-West, Idaho Falls, ID

    Cole, JI
    Argonne National Laboratory-West, Idaho Falls, ID

    Kenik, EA
    Oak Ridge National Laboratory, Oak Ridge, TN

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP10548S

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