W. Van Renterghem

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: In this article, irradiation-induced precipitates in a 304 stainless steel, neutron-irradiated to a dose of 24-dpa at 300-°C in the fuel wrapper plates of a commercial pressurized water reactor, were investigated by laser-assisted three-dimensional atom probe A high number density of 4 × 1023m−3 of Ni-Si rich precipitates was observed, which is one order of magnitude higher than that of Frank loops.

TL;DR: In this article, the radiation-induced segregation (RIS) of solute atoms at a grain boundary (GB) in 304 stainless steel (SS), neutron-irradiated to a dose of 24-dpa at 300-°C in the fuel wrapper plates of a commercial pressurized water reactor, was investigated using laser-assisted atom probe tomography (APT).

TL;DR: In this paper, the authors performed microstructural and micro-hardness measurements on a series of tungsten grades and found that the main contribution to the hardening at high irradiation temperature originates from the voids, while the dislocation loops provided a comparable contribution (30-50%) only under irradiation at 600-°C.