STP611: Development and Evaluation of a Stress-Free Swelling Correlation for 20 Percent Cold-Worked Type 316 Stainless Steel

    Garner, FA
    Senior research scientist, manager-Materials Development, and senior research scientist, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.

    Laidler, JJ
    Senior research scientist, manager-Materials Development, and senior research scientist, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.

    Guthrie, GL
    Senior research scientist, manager-Materials Development, and senior research scientist, Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.

    Pages: 19    Published: Jan 1976


    Abstract

    Sufficient data have been accumulated on the swelling behavior of 20 percent cold-worked Type 316 stainless steel to make predictions of the anticipated swelling in the fast test reactor (FTR). A predictive stress-free swelling correlation has been developed employing a limited data base developed in the Experimental Breeder Reactor-II (EBR-II). Insight gained from electron and ion simulation experiments aided in the correlation development. Application of this correlation to environments other than fast reactor core regions requires consideration of the differences in neutron spectrum and displacement rate in such environments.

    Keywords:

    radiation, irradiation, swelling, stainless steels, evaluation, nuclear reactors, voids


    Paper ID: STP38050S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP38050S


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