Abstracts and Available Papers Presented at the Meeting
Transmission Electron Microscopy Investigation of Irradiated U-7 wt% Mo Dispersion Fuel
S. Van den Berghe, W.
Van Renterghem and A. Leenaers
Nuclear Materials Science Institute, Microstructural and Non-destructive Analyses
SCK.CEN, Boeretang 200, 2400 Mol, Belgium
microstructural evolution of atomised U-7wt%Mo alloy
fuel under irradiation was investigated with
transmission electron microscopy on material from the
experimental fuel plates used in the FUTURE irradiation.
The unsatisfactory irradiation behaviour of this
atomised U(Mo) alloy dispersion fuel during this
experiment was derived to be related to the properties
of the interaction layer formed between the U(Mo)
particles and the Al matrix. It is assumed to become
amorphous under irradiation and as such cannot retain
the fission gas in stable bubbles. As a consequence, gas
filled voids are generated between the interaction layer
and the matrix, causing the fuel plate to swell,
resulting in failure.
The present analysis confirms the assumption that the U(Mo)-Al interaction layer is completely amorphous after the irradiation. The Al matrix and the individual U(Mo) particles, with their cellular substructure, have retained their crystallinity, although evidence for the amorphisation of the low Mo content phase on the cell boundaries is also found.
It was furthermore observed that the fission gas generated in the U(Mo) particles has formed a bubble superlattice which is coherent with the U(Mo) lattice. Bubbles of roughly 1-2 nm size formed a 3-dimensional lattice with a lattice spacing of 6-7 nm.
Full paper in PDF format
Transmission Electron Microscopy Investigation of
Irradiated U-7 wt% Mo Dispersion Fuel,
S. Van den Berghe et al.
[PDF, 1.6MB, 10 pages]
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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161