STP1490

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

    Published: Jan 2007


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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 code. This response was calculated for each reactor internal geometry that was irradiated by unit neutron flux which energy spectrum was calculated by the 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.

    Keywords:

    retrospective dosimetry, nondestructive, reactor internals, reactor vessel, HgI, 2, MCNP


    Author Information:

    Hayashi, Katsumi
    Hitachi Ltd., Ibaraki,

    Tayama, Ryuuichi
    Hitachi Ltd., Ibaraki,

    Watanabe, Yoshio
    Hitachi Ltd., Ibaraki,

    Nakamura, Tomomi
    Hitachi Ltd., Ibaraki,

    Kubota, Isamu
    Hitachi Engineering Company, Ibaraki,

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

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

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


    Paper ID: STP45420S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP45420S


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