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    Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures

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    Uniaxial fatigue properties from tests at 400, 500, 600, and 700 C on Type 304, 304L (Ti modified), and 316 stainless steel specimens irradiated at 450 C in sodium and 750 C in argon at fluences of 0.03 to 9.3×1021 n/cm2, E>0.1 MeV, are given and compared with control specimens. Material was tested in the annealed, cold-worked, and chilled-swaged-tempered condition, while primary controls received a pretest anneal of 1500 h at 750 C. The data at 400, 500, and 600 C are compared with proposed design curves for 18-8 steels. Some data on microstructural changes due to irradiation are given. A reduction in the fatigue life by a factor of less than 2.5 was found in the annealed material, which was attributed to irradiation damage. A beneficial effect on fatigue life of pretreatment by swaging was found after irradiation at 450 and 750 C for 2550 h.


    neutron irradiation, radiation effects, liquid metal cooled reactors, fast reactors (nuclear), stainless steels, helium, carbides, voids, microstructure, ductility, embrittlement, fatigue (materials), cold working, axial strains, mechanical properties, fatigue tests, high-temperature tests

    Author Information:

    Beeston, JM
    Idaho Nuclear Corp., Idaho Falls, Idaho

    Brinkman, CR
    Idaho Nuclear Corp., Idaho Falls, Idaho

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP26641S