STP1366

    Grain Boundary Phosphorus Segregation under Neutron Irradiation and Aging in 2.25Cr1Mo Steel

    Published: Jan 2000


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    Abstract

    Impurity segregation to grain boundaries under irradiation is one of the important radiation effects on materials. For this reason, phosphorus segregation to prior austenite grain boundaries in a P-doped 2.25Cr1Mo steel subjected to neutron irradiation and aging is examined using field emission gun scanning transmission electron microscopy (FEGSTEM) with energy dispersive X-ray microanalysis (EDX). The steel samples are irradiated and aged around 270 °C and 400 °C, respectively. The irradiation dose rate and dose are $#x223C;1.05×10-8 dpa/s and $#x223C;0.042 dpa respectively for 270 °C irradiation, and $#x223C;1.75×10-8 dpa/s and $#x223C;0.13 dpa respectively for 400 °C irradiation. The FEGSTEM results indicate that there is no apparent phosphorus segregation during 270 °C irradiation but there is some during 400 °C irradiation.

    Keywords:

    neutron irradiation, segregation, grain boundary, phosphorus


    Author Information:

    Song, S
    Researcher and Professor, Institute of Polymer Technology and Materials Engineering, Loughborough University, Loughborough,

    Faulkner, RG
    Researcher and Professor, Institute of Polymer Technology and Materials Engineering, Loughborough University, Loughborough,

    Hewitt, PEJ
    Structural Integrity Manager, Berkeley Centre, Magnox Electric plc, Berkeley, Gloucestershire,

    Marmy, P
    Senior Scientists, EPFL-CRPP, Fusion Technology, Villigen PSI,

    Victoria, M
    Senior Scientists, EPFL-CRPP, Fusion Technology, Villigen PSI,


    Paper ID: STP12400S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP12400S


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