Dosimetry assessments for the reactor pressure vessel and core barrel in UK pressurized water reactor (PWR) plant

D.A. Thornton, D.A. Allen, A.P. Huggon, D.J. Picton, A.T. Robinson, R.J. Steadman, Tom Seren, M. Lipponen, Tommi Kekki

    Research output: Contribution to journalArticle in a proceedings journalScientificpeer-review

    2 Citations (Scopus)


    Specimens for the Sizewell B reactor pressure vessel (RPV) inservice 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
    Original languageEnglish
    Pages (from-to)1-14
    JournalJournal of ASTM International
    Issue number4
    Publication statusPublished - 2012
    MoE publication typeA4 Article in a conference publication
    Event14th International Symposium on Reactor Dosimetry - Bretton Woods, NH, United States
    Duration: 22 May 201127 May 2011


    • Core barrel
    • MCBEND
    • Monte Carlo
    • pressurized water reactor
    • reactor pressure vessel
    • surveillance dosimetry


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