STP484

    Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures

    Published: Jan 1970


      Format Pages Price  
    PDF Version (696K) 30 $25   ADD TO CART
    Complete Source PDF (13M) 30 $166   ADD TO CART


    Abstract

    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.

    Keywords:

    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


    Paper ID: STP26641S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP26641S


    CrossRef ASTM International is a member of CrossRef.