3-D Fuel Burn Up Modeling with MCNP&ORIGEN-S

Silva Kalcheva, Edgar Koonen, Vadim Kuzminov

    Research outputpeer-review


    The purpose of this paper is to highlight the importance of the applied detailed 3-D fuel modeling in the highly heterogeneous, high flux MTR reactor BR2 for the accurate assessment of the reactor safety characteristics during the reactor operation. The combined MCNP&ORIGEN-S full-scale 3-D heterogeneous geometry model with detailed 3-D isotopic fuel profile in the whole core is used for the neutronics calculations. The effects of three burn up profiles on the reactivity variations are investigated: axial burn up profile in a fuel plate, radial in a fuel assembly and azimuth depletion profile in each axial segment of the annular fuel plates. The uncertainties in the maximum values of the heat flux due to different orientations of the fuel element in the core are estimated.
    Original languageEnglish
    Title of host publicationENS RRFM 2006: 10th International Meeting Research Reactor Fuel Management
    Place of PublicationBrussels, Belgium
    StatePublished - 18 Apr 2006
    Event2006 - RRFM - Research Reactor Fuel Management: 10th ENS Topical Meeting - European Nuclear Society, Sofia
    Duration: 30 Apr 20063 May 2006

    Publication series

    NameResearch Reactor Fuel Management


    Conference2006 - RRFM - Research Reactor Fuel Management

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