Spent nuclear fuel management, characterisation, and dissolution behaviour: Progress and achievement from SFC and DisCo

Anders Sjöland, Petra Christensen, Lena Zetterström Evins, Dirk Bosbach, Lara Duro, Ian Farnan, Volker Metz, Uwe Zencker, Jesus Ruiz-Hervias, Nieves Rodríguez-Villagra, Márton Király, Peter Schillebeeckx, Dmitri Rochman, Marcus Seidl, Ron Dagan, Marc Verwerft, Luis Enrique Herranz Puebla, Dmitri Hordynskyi, Francisco Feria, Efstathios Vlassopoulos

    Research outputpeer-review


    SFC is a work package in Eurad that investigates issues related to the properties of the spent nuclear fuel in the back-end of the nuclear fuel cycle. Decay heat, nuclide inventory, and fuel integrity (mechanical and otherwise), and not least the related uncertainties, are among the primary focal points of SFC. These have very significant importance for the safety and operational aspect of the back-end. One consequence is the operation economy of the back-end, where deeper understanding and quantification allow for significant optimization, meaning that significant parts of the costs can be reduced. In this paper, SFC is described, and examples of results are presented at about half-time of the work package, which will finish in 2024. The DisCo project started in 2017 and finished in November 2021 and was funded under the Horizon 2020 Euratom program. It investigated if the properties of modern fuel types, namely doped fuel, and MOX, cause any significant difference in the dissolution behavior of the fuel matrix compared with standard fuels. Spent nuclear fuel experiments were complemented with studies on model materials as well as the development of models describing the solid state, the dissolution process, and reactive transport in the near field. This research has improved the understanding of processes occurring at the interface between spent nuclear fuel and aqueous solution, such as redox reactions. Overall, the results show that from a long-term fuel matrix dissolution point of view, there is no significant difference between MOX fuel, Cr+Al-doped fuel, and standard fuels.

    Original languageEnglish
    Article number2022029
    Number of pages12
    JournalEPJ Nuclear Sciences and Technologies
    StatePublished - 21 Feb 2023

    ASJC Scopus subject areas

    • Nuclear and High Energy Physics
    • Energy Engineering and Power Technology
    • Electrical and Electronic Engineering
    • Nuclear Energy and Engineering

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