Volume 4, Issue 4 (April 2007)

    Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n)93Nbm and 54Fe(n,p)54Mn

    (Received 20 June 2005; accepted 28 March 2007)

    Published Online: 2007

    CODEN: JAIOAD

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    Abstract

    An overview is given of practices for “retrospective” dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence of the nuclide 60Co in the gamma-ray spectra of irradiated materials. Chemical separation of niobium and manganese is needed to determine the induced 93Nbm and 54Mn activities. Procedures have been developed for retrospective dosimetry applicable at normally equipped radiochemical laboratories. Chemical separation procedures have been applied followed by determination of the amount of niobium in dissolution after separation. Special attention has been given to the accurate counting of the very weak X rays of 93Nbm. Different techniques have been applied. Advantages, disadvantages, and the accuracy that can be achieved are discussed. Special attention has been given to the maximum accuracy that can be reached and the minimum amount of niobium that has to be collected to reach this accuracy.


    Author Information:

    Voorbraak, W. P.
    MMI-Monitoring, Netherlands Research and Consultancy Group NRG,

    Kekki, T.
    VTT Technical Research Centre of Finland, VTT,

    Serén, T.
    VTT Technical Research Centre of Finland, VTT,

    Van Bockxstaele, M.
    SCK-CEN,

    Wagemans, J.
    SCK-CEN, Reactor Physics & Myrrha Department,

    Woittiez, J. R.W.
    Medical Applications, Netherlands Research and Consultancy Group NRG,


    Stock #: JAI101142

    ISSN: 1546-962X

    DOI: 10.1520/JAI101142

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    Author
    Title Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n)93Nbm and 54Fe(n,p)54Mn
    Symposium Reactor Dosimetry, 12th International Symposium, 2005-05-13
    Committee E10