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Evaluation of the long-term behavior of potential plutonium waste forms in a geological repository

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  1. Article

    Open Access

    Caesium and iodine release from spent mixed oxide fuels under repository relevant conditions: Initial leaching results

    Autoclave leaching experiments are conducted on three well-characterised, irradiated, and cladded mixed oxide fuel-rod segments with burnups ranging from 29 GWd/tHM to 52 GWd/tHM to investigate the instant releas...

    Christian Schreinemachers, Gregory Leinders, Thierry Mennecart… in MRS Advances (2022)

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  2. Article

    Open Access

    Accelerated dissolution of doped UO2-based model systems as analogues for modern spent nuclear fuel under repository conditions

    Systematic single-effect dissolution studies were carried out on the dissolution behaviour of pure and Cr- or Nd-doped UO2 reference pellets as model materials for spent nuclear fuel with varying do** levels, d...

    Philip Kegler, Stefan Neumeier, Martina Klinkenberg, Andrey Bukaemskiy… in MRS Advances (2023)

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