Effects of fuel temperature history approximations on neutronics properties of a BWR assembly

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    We study the effects of fuel temperature approximation made in the history part of group constant generation for a boiling water reactor (BWR) assembly. We compare produced nuclide densities and group constants when the burnup calculation in the history part uses either realistic fuel temperatures provided by a fuel performance code or an effective flat and constant fuel temperature. The results mirror our previous findings for PWR assemblies: The fuel temperature approximation has a noticeable effect on gadolinium burnout and production of fissile actinides. Differences in the actinide content of the assembly are further reflected into homogenized absorption and fission cross sections at high burnups.
    Original languageEnglish
    Title of host publicationProceedings of the PHYSOR 2018, Cancun, Mexico
    PublisherAmerican Nuclear Society (ANS)
    Number of pages12
    Publication statusPublished - 2018
    MoE publication typeA4 Article in a conference publication
    EventPHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems - Cancun, Mexico
    Duration: 22 Apr 201826 Apr 2018


    ConferencePHYSOR 2018
    Abbreviated titlePHYSOR 2018

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