STP782

    An In-Reactor Creep Correlation for 20% Cold Worked AISI 316 Stainless Steel

    Published: Jan 1982


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    Abstract

    An empirical in-reactor creep equation has been developed for 20% cold worked 316SS. This equation is based upon creep data obtained predominately from pressurized tube specimens irradiated in the Experimental Breeder Reactor EBR-II at specific irradiation temperatures between 400 and 730°C and to a peak fluence of 7×1022n/cm2 (E >0.1 MeV). The correlation includes both thermal and irradiation induced creep terms to model the observed primary, steady-state, and tertiary creep behaviors for this alloy. The thermal creep tertiary term has been modified to reflect the observed delay in the onset of tertiary creep for the in-reactor creep data. The correlation is compared to the in-reactor data base and the 1σ uncertainty has been found to be 30% of the calculated strain where data exist.

    Keywords:

    stainless steel, creep, irradiation, model, 316SS


    Author Information:

    Puigh, RJ
    Senior scientist, Westinghouse Hanford Company, Richland, Washington

    Gilbert, ER
    Senior engineer, Pacific Northwest Laboratory, Richland, Washington

    Chin, BA
    Associate professor, Auburn University, Auburn, Alabama


    Paper ID: STP34341S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP34341S


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