Neutron-induced nuclear data for the MYRRHA fast spectrum facility

P. Romojaro, G. Zerovnik, F. Alvarez-Velarde, Alexey Stankovskiy, I. Kodeli, Luca Fiorito, C.J. Diez, O. Cabellos, N. Garcia-Herranz, J. Heyse, C. Paradela, P. Schillebeeckx, Gert Van den Eynde

    Research outputpeer-review


    The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta)Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.
    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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