Volume 3, Issue 7 (July 2006)

    Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel

    (Received 20 June 2005; accepted 24 May 2006)

    CODEN: JAIOAD

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    Abstract

    Nondestructive and simple retrospective dosimetry method was developed. Mercuric iodide or cadmium zinc telluride detector was used as a detector to measure 54Mn, 58Co, and 60Co that were created in reactor internals and vessels. Detector is surrounded by tungsten collimator which shield background gamma rays and detect gamma rays from desired measuring point. Photopeak count rate of this detector were calculated using the MCNP-4C code. This response was calculated for each reactor internal geometry that was irradiated by unit neutron flux which energy spectrum was calculated by the TORT code. Neutron fluence is calculated using precalculated response, measuring time, decay time and reactor power history. We can also get Displacement per Atom (DPA), hydrogen and helium production simultaneously using neutron spectrum precalculated in reactor vessel. Because the time and cost of this method are much less than the sampling method, we can measure at many positions and even get a contour map.


    Author Information:

    Hayashi, K
    Hitachi Ltd., Ibaraki,

    Tayama, R
    Hitachi Ltd., Ibaraki,

    Watanabe, Y
    Hitachi Ltd., Ibaraki,

    Nakamura, T
    Hitachi Ltd., Ibaraki,

    Kubota, I
    Hitachi Engineering Company, Ibaraki,

    Hayashi, H
    Chubu Electric Power Co., Inc., Aichi,

    Yamasaki, T
    Chubu Electric Power Co., Inc., Aichi,

    Yuya, H
    Chubu Electric Power Co., Inc., Aichi,


    Stock #: JAI100359

    ISSN: 1546-962X

    DOI: 10.1520/JAI100359

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    Author
    Title Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel
    Symposium Reactor Dosimetry, 12th International, 2005-05-13
    Committee E10