Volume 4, Issue 8 (September 2007)

    Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels

    (Received 21 June 2006; accepted 27 July 2007)

    Published Online: 2007

    CODEN: JAIOAD

      Format Pages Price  
    PDF Version 12 $25   ADD TO CART


    Abstract

    A study on phosphorus (P) segregation at grain boundaries and intergranular embrittlement of reactor pressure vessel steels due to thermal aging and neutron irradiation has been performed for A533B steel plates and weld metals doped with different bulk levels of P. The initial P concentration at grain boundaries of these materials determined by scanning Auger microscopy ranged from 9 to 33 %. The materials thermally aged at temperatures ranging from 450 to 550°C for up to 10000 h exhibited increases in P concentration described by the McLean’s equation. A linear correlation was obtained between P concentration and Charpy 41 J transition temperature (T41J). Fracture toughness tests in the ductile-to-brittle transition temperature region have been conducted by the Master Curve method using 1T-CT specimens. The material subject to intergranular embrittlement exhibited the dual fracture toughness distributions typically observed in inhomogeneous materials. This was probably due to two types of initiation of cleavage and intergranular fracture. The lower tail analysis based on the Master Curve method enabled conservative fracture toughness estimates by fitting the lower fracture toughness arising from intergranular fracture. The relation between median KJc values estimated from the lower tail analysis and temperature appeared to follow the Master Curve. For neutron irradiated materials up to a fluence of 6.9×1019 n/cm2 (E>1 MeV) at 290°C by the Japan Materials Testing Reactor, an increase in grain boundary P segregation associated with decrease in carbon segregation was observed with increasing fluence. Relative significant hardening was recognized for the material with high bulk P content. Shifts in the reference temperature T0 and T41J were comparable for the thermally aged and irradiated materials.


    Author Information:

    Nishiyama, Yutaka
    Nuclear Reactor Safety Research Center, Japan Atomic Energy Agency, Tokai-Mura, Ibaraki-Ken

    Onizawa, Kunio
    Nuclear Reactor Safety Research Center, Japan Atomic Energy Agency, Tokai-Mura, Ibaraki-Ken

    Suzuki, Masahide
    Nuclear Reactor Safety Research Center, Japan Atomic Energy Agency, Tokai-Mura, Ibaraki-Ken


    Stock #: JAI100690

    ISSN: 1546-962X

    DOI: 10.1520/JAI100690

    ASTM International is a member of CrossRef.

    Author
    Title Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels
    Symposium 23rd Symposium on Effects of Radiation on Materials, 2006-06-15
    Committee E10