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

W. P. Voorbraak, Tommi Kekki, Tom Serén, M. Van Bockxstaele, J. Wagemans, J. R. W. Woittiez

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review


    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.
    Original languageEnglish
    Title of host publicationReactor Dosimetry: 12th International Symposium on
    EditorsDavid Vehar, David Gilliam, James Adams
    Place of PublicationWest Conshohocken
    PublisherAmerican Society for Testing and Materials (ASTM)
    ISBN (Print)978-0-8031-3412-6, 978-0-8031-6242-6
    Publication statusPublished - 2007
    MoE publication typeA4 Article in a conference publication
    Event12th International Symposium on Reactor Dosimetry - Gatlinburg, TN, United States
    Duration: 8 May 200513 May 2005

    Publication series

    SeriesASTM Special Technical Publication


    Conference12th International Symposium on Reactor Dosimetry
    Country/TerritoryUnited States
    CityGatlinburg, TN


    • retrospective dosimetry
    • neutron fluence
    • neutron damage
    • niobium
    • manganese
    • column anion exchange
    • liquid scintillation counting
    • neutron activation analysis


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