Volume 4, Issue 7 (July 2007)

    Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels

    (Received 5 June 2007; accepted 17 July 2007)

    Published Online: 2007

    CODEN: JAIOAD

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    Abstract

    A new approach of utilizing information fusion technique is developed to predict the radiation embrittlement of reactor pressure vessel steels. The Charpy transition temperature shift data contained in the Power Reactor Embrittlement Database is used in this study. Six parameters—Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature—are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5 % and 52 % in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.


    Author Information:

    Wang, J. A.
    Oak Ridge National Laboratory, Oak Ridge,

    Rao, N. S. V.
    Oak Ridge National Laboratory, Oak Ridge,

    Konduri, S.
    Oak Ridge National Laboratory, Oak Ridge,


    Stock #: JAI100681

    ISSN: 1546-962X

    DOI: 10.1520/JAI100681

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    Author
    Title Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels
    Symposium 23rd Symposium on Effects of Radiation on Materials, 2006-06-15
    Committee E10