STP457: Development of Austenitic Stainless Steels with Improved Resistance to Elevated-Temperature Irradiation Embrittlement

    Bloom, E. E.
    MetallurgistAssociate Member of ASTM, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Weir, J. R.
    Section Head, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Pages: 29    Published: Jan 1969


    Abstract

    The effects of titanium in concentrations of up to 0.5 weight percent on the tensile and creep-rupture properties of unirradiated and irradiated types 304 and 304L stainless steel have been investigated. It was found that within this range an alloy containing 0.15 to 0.25 weight percent titanium has optimum postirradiation ductility. When this alloy is annealed 1 h at 925 C prior to irradiation, the postirradiation ductility is essentially independent of tension test temperature and increases as the strain rate is reduced in creep-rupture tests at 700 C. In contrast, the postirradiation ductility of standard types 304 or 304L stainless steel heat treated and irradiated under the same conditions decreases with increasing temperature or decreasing strain rate.

    These effects appear to result primarily from the effect of titanium on the intergranular fracture process, making crack initiation or propagation, or both, more difficult and thus reducing susceptibility to the high-temperature irradiation embrittlement phenomenon.

    Keywords:

    stainless steels, high temperature tests, irradiation, embrittlement, mechanical properties, tests, evaluation


    Paper ID: STP41851S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP41851S


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