Modelling oriented investigations of primary radiation damage in ultra high purity Fe and FeCr alloys
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Thermonuclear fusion of light atoms is considered since decades as an unlimited, safe and reliable source of energy that could eventually replace classical sources based on fossile fuel or nuclear fuel. Fusion reactor technology and materials studies are i ...
In the quest of materials for the first wall of the future fusion reactor, it has been shown that oxide dispersion strengthened (ODS) ferritic / martensitic (F/M) steels appear to be promising candidates. The inherent good mechanical properties supported b ...
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Intergranular penetration of liquid bismuth has been analysed in two pure metals, Cu at 500°C and Ni at 700°C, used either as polycrystals or as oriented bicrystals. At the liquid/solid interface, large grooves have developed in Cu-Bi, while micrometer-thi ...
Ferritic/martensitic (F/M) steels show good resistance to swelling and low damage accumulation upon irradiation relative to stainless steels. 0.3 wt% yttria particles were added to the F/M steel EUROFER 97 to produce oxide dispersion strengthened (ODS) ste ...
Low activation ferritic/martensitic steels are good candidates for the future fusion reactors, for, relative to austenitic steels, their lower damage accumulation and moderate swelling under irradiation by the 14 MeV neutrons produced by the fusion reactio ...
Beams of electrons and ions are now fairly routinely focused to dimensions in the nanometer range. Since the beams can be used to locally alter material at the point where they are incident on a surface, they represent direct nanofabrication tools. The aut ...