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Determination of the Spent Fuel Decay Heat with the VERA Core Simulator

  • Marjan Kromar
  • , Andrew T. Godfrey

    Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

    Abstract

    VERA core simulator capabilities to predict spent fuel decay heat have been explored. Comparison with the Serpent2 and NEWT/TRITON sequence from the SCALE package, performed on the NPP Krško fuel test cases, has enabled the validation of the VERA calculation sequence. Since the VERA is a 3-D core simulator, the focus in the rest of the paper was on the investigation of the 3-D effects and nonlinearity of the soluble boron concentration averaging process, which are difficult to assess with majority of available calculation tools. A difference in the decay heat prediction between the 3-D and 2-D model approaches has been analyzed. In addition, the impact of the Inconel grids on the decay heat was determined. Averaging of the soluble boron concentration over the fuel irradiation period has been found to be a viable approach, since it results in slight decay heat overprediction, which is considered conservative for the most applications. Finally, demonstration on the Watts Bar Unit 1 cycle 1 depletion has shown formidable VERA capabilities to accurately predict spent fuel decay heat.

    Original languageEnglish
    Title of host publicationProceedings of the International Conference on Physics of Reactors, PHYSOR 2022
    PublisherAmerican Nuclear Society
    Pages166-175
    Number of pages10
    ISBN (Electronic)9780894487873
    DOIs
    StatePublished - 2022
    Event2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States
    Duration: May 15 2022May 20 2022

    Publication series

    NameProceedings of the International Conference on Physics of Reactors, PHYSOR 2022

    Conference

    Conference2022 International Conference on Physics of Reactors, PHYSOR 2022
    Country/TerritoryUnited States
    CityPittsburgh
    Period05/15/2205/20/22

    Funding

    Presented research was made possible by the Consortium for Advanced Simulation of Light Water Reactors (www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors. This work has used HPC resources at INL.

    Keywords

    • CASL
    • VERA
    • core simulator
    • decay heat
    • spent nuclear fuel

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