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    STP1608

    Retrospective Dosimetry Analysis of Top Support Plug Samples from Scrap Surveillance Capsule Material for Qualifying Calculations in the Extended Beltline Region of PWRS

    Published: 2018


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    Abstract

    This paper describes a retrospective dosimetry analysis of stainless steel samples collected from discarded surveillance capsules that were irradiated at Westinghouse two-loop and three-loop pressurized water reactor plants. The samples were taken from top support plugs and extender bars, which extend as much as 55 cm above the top of the core, and are conveniently located between the top of the core and the reactor vessel nozzles. Comparisons of measurements with the results of three-dimensional deterministic radiation transport calculations are provided. Major sources of uncertainty affecting the calculations and measurements are discussed. Finally, industry plans to collect additional qualification data will be summarized.

    Keywords:

    reactor dosimetry, neutron dosimetry, retrospective dosimetry, surveillance capsule dosimetry, neutron fluence


    Author Information:

    Fischer, Greg A.
    Radiation Engineering and Analysis, Westinghouse Electric Co., LLC, PA

    Kim, Byoung Chul
    Korea Reactor Integrity Surveillance Technology, Daejeon,


    Committee/Subcommittee: E10.05

    DOI: 10.1520/STP160820170073