Decay heat uncertainty quantification of MYRRHA

    Research outputpeer-review


    MYRRHA is a lead-bismuth cooled MOX-fueled accelerator driven system (ADS) currently in the design phase at SCK•CEN in Belgium. The correct evaluation of the decay heat and of its uncertainty level is very important for the safety demonstration of the reactor. In the first part of this work we assessed the decay heat released by the MYRRHA core using the ALEPH-2 burnup code. The second part of the study focused on the nuclear data uncertainty and covariance propagation to the MYRRHA decay heat. Radioactive decay data, independent fission yield and cross section uncertainties/covariances were propagated using two nuclear data sampling codes, namely NUDUNA and SANDY. According to the results, 238U cross sections and fission yield data are the largest contributors to the MYRRHA decay heat uncertainty. The calculated uncertainty values are deemed acceptable from the safety point of view as they are well within the available regulatory limits.
    Original languageEnglish
    Title of host publicationEPJ Web of Conferences
    Subtitle of host publicationND 2016: International conference on nuclear data for science and technology
    Number of pages4
    StatePublished - 18 Sep 2017
    Event2016 - ND: International Conference on Nuclear Data for Science and Technology - Concert gebouw en Oud Sint Jan Hospitaal, Bruges
    Duration: 11 Sep 201616 Sep 2016

    Publication series

    NameEPJ Web of Conferences
    PublisherEDP Sciences
    ISSN (Print)2100-014X


    Conference2016 - ND
    Abbreviated titleND2016
    Internet address

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering

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