Ann Leenaers

TL;DR: In this article, two low-enriched uranium fuel plates consisting of U-7wt%Mo atomized powder dispersed in an aluminum matrix, have been irradiated in the FUTURE irradiation rig of the BR2 reactor at SCK•CEN.

TL;DR: In this paper, the microstructural evolution of atomised U-7-wt%Mo alloy fuel under irradiation was investigated by transmission electron microscopy on material from the experimental fuel plates used in the FUTURE irradiation.

TL;DR: In this article, the authors reported the post irradiation examination results obtained on four IRIS-TUM plates with and without the addition of silicon (2.1 × 2.1 µm) and showed that the observed moderate but positive effect of Si as inhibitor for the U(Mo)−Al interaction is related to the dispersion of this element in the interaction layer, although its concentration is very inhomogeneous and appears to be too low to fully inhibit interaction layer growth.

TL;DR: Since the 1970's, global efforts have been going on to replace the high-enriched (>90% 235U), low-density UAlx research reactor fuel with high-density, low enriched (

TL;DR: The European LEONIDAS program as discussed by the authors is aimed at the qualification of such a fuel for the use in high power conditions, and the first experiment of the program, designated E-FUTURE, was performed to select the appropriate matrix Si concentration and fuel plate post-production heat treatment parameters.