STP1490: Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant

    Allen, D. A.
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

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

    Thornton, D. A.
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Fletcher, A. L.
    British Nuclear Group, Berkeley Centre, Berkeley, Gloucestershire

    Bird, A. J.
    Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

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

    Wright, G. A.
    Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset

    Pages: 8    Published: Jan 2007


    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.

    Keywords:

    decommissioning, radioactive inventory, magnox power plant, monte carlo, MCBEND


    Paper ID: STP45455S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP45455S


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