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Determination of the spent fuel decay heat with the VERA core simulator

  • Marjan Kromar
  • , Andrew T. Godfrey

    Research output: Contribution to journalArticlepeer-review

    5 Scopus citations

    Abstract

    VERA core simulator capabilities to predict spent fuel decay heat have been explored. The comparison with the Serpent2 and NEWT/TRITON sequence from the SCALE package, performed on the NPP Krško fuel test cases, has enabled independent verification of the successful implementation of the VERA depletion/decay calculation sequence applied on the extended nuclide set. 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 non-linearity of the soluble boron concentration averaging process, which are difficult to assess with most of available computational tools. A difference in the decay heat prediction between the 3-D and 2-D model approaches was analyzed. In addition, the impact of the Inconel grids on the decay heat was determined. Averaging the concentration of soluble boron 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 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
    Article number1046506
    JournalFrontiers in Energy Research
    Volume10
    DOIs
    StatePublished - Dec 19 2022

    Funding

    Presented research was made possible through collaboration with the VERA Users Group ( https://vera.ornl.gov/ ). This research made use of the resources of the High-Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. MK acknowledges the financial support from the Slovenian Research Agency (research core funding No. P2-0073).

    Keywords

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

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