STP529: High-Temperature Embrittlement of Ferritic and Austenitic Stainless Steels Irradiated up to 1.6 × 1022 n/cm2 (> 0.1 MeV)

    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,

    Pages: 11    Published: Jan 1973


    Abstract

    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.

    Keywords:

    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


    Paper ID: STP35460S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP35460S


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