Title: Characterization of self-damaged (U,Pu)N fuel used in the NIMPHE program
Authors: CARVAJAL NUNEZ URSULAPRIEUR DAMIENJANSSEN ARNEWISS ThierryCAMBRIANI ANDREAVERMOREL EmmanuelScheinost A.C.SOMERS Joseph
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 443 p. 491 - 496
Publisher: ELSEVIER SCIENCE BV
Publication Year: 2013
JRC N°: JRC82764
ISSN: 0022-3115
URI: http://www.sciencedirect.com/science/article/pii/S0022311513009574
http://publications.jrc.ec.europa.eu/repository/handle/JRC82764
DOI: 10.1016/j.jnucmat.2013.07.069
Type: Articles in periodicals and books
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.
JRC Directorate:Nuclear Safety and Security

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