Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant

    Volume 3, Issue 6 (June 2006)

    ISSN: 1546-962X

    CODEN: JAIOAD

    Published Online: 5 April 2006

    Page Count: 8


    Allen, DA
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Thiruarooran, C
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Thornton, DA
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Fletcher, AL
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Bird, AJ
    Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

    Rycroft, S
    Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

    Wright, GA
    Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

    (Received 20 June 2005; accepted 5 February 2006)

    Abstract

    This paper describes the methodology and results of Monte Carlo neutron transport calculations performed to determine the neutron fluxes required for assessments of radioactive inventories of Magnox power plant. Use has been made of existing validated Monte Carlo models of the plant, which have been extended to include details beyond the pressure vessels to the outer surface of the biological shield.


    Paper ID: JAI100364

    DOI: 10.1520/JAI100364

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    Author
    Title Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
    Symposium Reactor Dosimetry, 12th Volume, 2005-05-13
    Committee E10