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    The Flow and Fracture Properties of Unirradiated Stainless Steels


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    The effects of nuclear radiation on the engineering properties of austenitic stainless steels can best be understood by comparing the properties of the unirradiated steels with those after irradiation. Factors which may influence the properties of stainless steels in the unirradiated condition are reviewed from the standpoint of chemical composition, manufacturing practice, and thermal treatment for the four most common austenitic grades: AISI Types 304, 316, 321, and 347.

    Author Information:

    Beeghly, H. F.
    Senior research associate, Graham Research Laboratory, Jones and Laughlin Steel Corp., Pittsburgh, Pa.

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP43531S