Characterization of self-damaged (U,Pu)N fuel used in the NIMPHE program

Ursula Carvajal-Nunez, Damien Prieur, Arne Janssen, Thierry Wiss, Andrea Cambriani, Emmanuel Vermorel, Andreas Scheinost, Joseph Somers

    Research output: Contribution to journalArticlepeer-review

    Abstract

    During in-pile, irradiation-induced damage occurs in nuclear fuel and results in a deterioration of its properties, which can affect the margin to melt of the fuel. Damage also occurs in fresh fuel through the self-irradiation process, and thus provides a convenient means to investigate changes in the material. A uranium-plutonium mixed nitride fuel made over 25 years ago, and stored in the ITU archives has been retrieved. Coupling EXAFS and TEM has shown that this material was still well-crystallized. However, an increase of 0.3% of the lattice parameter was found. As shown by the EXAFS, the U-N and Pu-N as well as the metal-metal distances are similarly affected. However, no significant modification of both anion and cation sublattice was found. Although no defect clustering was found by EXAFS, the presence of nanometric helium bubbles was demonstrated by TEM as well as nanometric disordered domains. © 2013 Elsevier B.V. All rights reserved.
    Original languageEnglish
    Pages (from-to)491-496
    Number of pages5
    JournalJournal of Nuclear Materials
    Volume443
    Issue number1-3
    Publication statusPublished - 2013

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