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    STP1398

    Retrospective Fast Neutron Dosimetry of Nuclear Power Plants by Means of Scraping Samples Using the 93Nb(n,n')93mNb Reaction

    Published: 0


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    Abstract

    Steel samples from a core component of a boiling water reactor have been investigated in order to determine the accumulated fast neutron fluence. The study was performed by means of the reaction 93Nb(n,n')93mNb. For this examination, the steel samples were taken after having been irradiated during normal operation for about 20 years. Starting with chemical separation methods, the specific activity of 93mNb in the steel samples was measured by a) inductively coupled plasma mass spectrometry, and b) total reflection X-ray fluorescence technique. From these results, the fast neutron fluence for neutron energies above 1 MeV were calculated. The fluence values determined using inductively coupled plasma mass spectrometry are in good agreement with earlier 54Mn measurements.

    Keywords:

    retrospective reactor dosimetry, fast neutron fluence, niobium method, inductively coupled plasma mass spectrometry, total reflection X-ray fluorescence analysis


    Author Information:

    van Aarle, J
    Swiss Federal Nuclear Safety Inspectorate, Villigen-HSK,

    Guenther, I
    Laboratory for Materials Behaviour, Paul Scherrer Institute, Villigen-PSI,

    Hegedues, F
    X-Ray Consulting, Villigen-PSI,

    Gabler, F
    Laboratory for Materials Behaviour, Paul Scherrer Institute, Villigen-PSI,


    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP13658S