STP1550

    Dosimetry Assessments for the Reactor Pressure Vessel and Core Barrel in UK Pressurized Water Reactor (PWR) Plant

    Published: Aug 2012


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    Abstract

    Specimens for the Sizewell B reactor pressure vessel (RPV) in-service steels surveillance program are irradiated inside eight capsules located within the reactor pressure vessel and loaded prior to commissioning. The periodic removal of these capsules and testing of their contents provides material properties data at intervals during the lifetime of the plant. Neutron activation measurements and radiation transport calculations play an essential role in assessing the neutron exposure of the specimens and RPV. Following the most recent withdrawal, seven capsules have now been removed covering nine cycles of reactor operation. This paper summarizes the dosimetry results of the Sizewell B surveillance program obtained to date. In addition to an overview of the calculational methodology it includes a review of the measurements. Finally, it describes an extension of the methodology to provide dosimetry recommendations for the core barrel and briefly discusses the results that were obtained.

    Keywords:

    pressurized water reactor, surveillance dosimetry, reactor pressure vessel, core barrel, Monte Carlo, MCBEND


    Author Information:

    Thornton, D. A.
    Serco, Gloucester,

    Allen, D. A.
    Serco, Gloucester,

    Huggon, A. P.
    Serco, Gloucester,

    Picton, D. J.
    Serco, Gloucester,

    Robinson, A. T.
    Serco, Gloucester,

    Steadman, R. J.
    Serco, Gloucester,

    Serén, T.
    VTT, Technical Research Centre of Finland, Espoo,

    Lipponen, M.
    VTT, Technical Research Centre of Finland, Espoo,

    Kekki, T.
    VTT, Technical Research Centre of Finland, Espoo,


    Paper ID: STP155020120003

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120003


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