High-Temperature Embrittlement of Ferritic and Austenitic Stainless Steels Irradiated up to 1.6 × 1022 n/cm2 (> 0.1 MeV)

    Published: Jan 1973

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    Tension specimens of four basic stainless steels having a body-centered cubic (bcc) or face-centered cubic (fcc) structure without or with nickel addition have been fabricated by casting and by powder metallurgy (without and with TiO2 addition). These specimens have been irradiated at 60 C (140 F) up to a 1.6 × 1022 n/cm2 fast fluence (> 0.1 MeV) and ruptured at 700 C (1292 F). A structural and statistical analysis shows that bcc structure, powder metallurgy fabrication methods, TiO2 additions, and transgranular rupture enhance the 700 C resistance to fast neutron embrittlement. The degree of embrittlement is related to the rupture mode before irradiation.


    irradiation, neutron irradiation, radiation effects, tension tests, ductility, elongation, microstructure, embrittlement, grain boundaries, cracking, failure, crystal structure, dispersions, dispersion hardening, powder metallurgy, alloys, ferritic stainless steels, austenitic stainless steels

    Author Information:

    Van Asbroeck, P
    Centre d' Etude de l'Energie Nucleaire, C.E.N./S.C.K., MOL,

    Snykers, M
    Centre d' Etude de l'Energie Nucleaire, C.E.N./S.C.K., MOL,

    Vandermeulen, W
    Centre d' Etude de l'Energie Nucleaire, C.E.N./S.C.K., MOL,

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP35460S

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