An Inline Burnup Algorithm

P. Cosgrove*, E. Shwageraus, Jaakko Leppänen

*Corresponding author for this work

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    Inline algorithms have been proposed for coupling Monte Carlo neutron transport solvers with several other physics, such as xenon and iodine densities and thermal hydraulics. This paper proposes a new inline algorithm that can be applied to burnup calculations. The algorithm is a modification of the predictor-corrector method, where the corrector-step nuclide densities are converged simultaneously with the fission source. This could, in principle, obviate the need for two full neutronics solutions per time-step while still allowing the accuracy of predictor-corrector methods with improved stability. This paper describes the algorithm and demonstrates its stability properties through a Fourier analysis. Although not unconditionally stable, judicious use of batching and relaxation are shown to greatly improve the algorithm’s stability properties in realistic systems.

    Original languageEnglish
    Pages (from-to)1681-1699
    JournalNuclear Science and Engineering
    Volume197
    Issue number8
    DOIs
    Publication statusPublished - 2023
    MoE publication typeA1 Journal article-refereed

    Keywords

    • burn up
    • Monte Carlo
    • Neutronics
    • stability

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