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

    Volume 3, Issue 4 (April 2006)

    ISSN: 1546-962X

    CODEN: JAIOAD

    Page Count: 7


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

    Böhmer, B
    Guest ScientistForschungszentrum 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,

    (Received 20 June 2005; accepted 29 September 2005)

    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 cross-sectional groups on the calculation results is demonstrated.


    Paper ID: JAI13460

    DOI: 10.1520/JAI13460

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    Author
    Title Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data
    Symposium , 0000-00-00
    Committee E10