Publikationsrepositorium - Helmholtz-Zentrum Dresden-Rossendorf

Uranium–americium mixed oxides are promising fuels for achieving an efficient Am recycling. Previous studies on U0.85Am0.15O27x materials showed that the high a activity of 241Am induces pellet swelling which is a major issue for cladding materials design. In this context, X-ray Diffraction and X-ray Absorption Spectroscopy measurements were used to study self-irradiation effects on U0.85Am0.15O27x local structure and to correlate these results with those obtained at the macroscopic scale. For a cumulative a decay dose equal to 0.28 dpa, it was shown that non-defective fluorite solid solutions were achieved and therefore, that the fluorite structure is stable for the studied doses. In addition, both interatomic distance and lattice parameter expansions were observed, which only partially explains the macroscopic swelling. As expected, an increase of the structural disorder with self-irradiation was also observed.