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    Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

    Published: 01 January 2010

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    A study on grain-boundary segregation and embrittlement in terms of the Charpy ductile-to-brittle transition temperature (DBTT) has been performed for the neutron-irradiated A533B steels with typical contents of impurities of Japanese reactor pressure vessel ones. The neutron irradiation was conducted at 563 K to a fluence of 1.3 × 1024n/m2 (E>1 MeV) using material testing reactors. The neutron irradiation induced the P and Ni segregation and the reduction in C in some cases at grain-boundaries. The increase in the P segregation at high fluence (>5 × 10 23n/m2, E>1 MeV) was less than 0.1 in monolayer coverage for the steels with the bulk content of P not exceeding 0.02 wt%. The hardening more strongly affected the DBTT shift than the P segregation for those steels. The reduction in segregated C that enhances the grain-boundary cohesion by neutron fluence is not large enough to cause the DBTT shift.


    reactor pressure vessel, phosphorus segregation, carbon segregation, grain-boundary, neutron irradiation, embrittlement, ductile-to-brittle transition temperature (DBTT), intergranular fracture

    Author Information:

    Nishiyama, Yutaka
    Japan Atomic Energy Agency, Ibaraki-ken,

    Yamaguchi, Masatake
    Japan Atomic Energy Agency, Ibaraki-ken,

    Onizawa, Kunio
    Japan Atomic Energy Agency, Ibaraki-ken,

    Iwase, Akihiko
    Osaka Prefecture Univ., Osaka,

    Matsuzawa, Hiroshi
    Japan Nuclear Energy Safety Organization, Tokyo,

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP49007S