Fatigue Response and Life Prediction of Selected Reactor Materials

    Volume 1, Issue 5 (May 2004)

    ISSN: 1546-962X

    CODEN: JAIOAD

    Published Online: 3 May 2004

    Page Count: 14


    Li, M
    University of Illinois at Urbana-Champaign. Current Address: Oak Ridge National Laboratory, Oak Ridge, TN

    Stubbins, JF
    Professor and Head, University of Illinois at Urbana-Champaign, 214 Nuclear Engineering Laboratory, Urbana, IL

    (Received 22 July 2002; accepted 30 January 2003)

    Abstract

    This paper analyzes experimental fatigue response for selected unirradiated and irradiated reactor materials: AISI 316 stainless steel, ferritic/martensitic MANET and HT9 steels. Available tensile test results on the same or similar materials are used to predict changes in fatigue response using the Universal Slopes method. The predictions are compared with the experimental data to assess the potential for using tensile data to predict reactor component fatigue response. It was found that the effect of irradiation on fatigue life was less severe than on tensile properties. However, tensile properties are useful for qualitative predictions of fatigue response.


    Paper ID: JAI11334

    DOI: 10.1520/JAI11334

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    Author
    Title Fatigue Response and Life Prediction of Selected Reactor Materials
    Symposium The Effects of Radiation on Materials: 21st International Symposium, 2002-06-20
    Committee E10