STP1490

    Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data

    Published: Jan 2007


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    Abstract

    The results of a study of neutron and gamma field functionals derived by deterministic Sn and Monte Carlo calculation methods and by neutron activation measurements in application to the ex-vessel cavity of the VVER-440 reactor Greifswald-1 are presented. A good agreement of deterministic and stochastic calculation results with each other as well as with measurement results was found for neutron threshold detector reaction rates at ex-vessel positions. The influence of different numbers of crosssectional groups on the calculation results is demonstrated.

    Keywords:

    VVER, neutron-gamma transport calculation, ex-vessel activation measurements


    Author Information:

    Borodkin, G.
    Head of Reactor Dosimetry Group (Borodkin), Head of Department (Khrennikov), Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadzor, Moscow,

    Khrennikov, N.
    Head of Reactor Dosimetry Group (Borodkin), Head of Department (Khrennikov), Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadzor, Moscow,

    Böhmer, B.
    Guest Scientist, Forschungszentrum Rossendorf e.V. (FZR), Dresden,

    Noack, K.
    Head of Department (Noack), Research Scientist (Konheiser), Forschungszentrum Rossendorf e.V. (FZR), Dresden,

    Konheiser, J.
    Head of Department (Noack), Research Scientist (Konheiser), Forschungszentrum Rossendorf e.V. (FZR), Dresden,


    Paper ID: STP45450S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP45450S


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