Two ferritic Oxide Dispersion Strengthened (ODS) steels Fe-12Cr-YWT and Fe-14Cr-YWT were irradiated in the High Flux Reactor (HFR) up to 3 dpa at a nominal temperature of 600°C. Tensile tests at room and elevated temperatures as well as microstructural investigations using transmission electron microscopy (TEM) and atom probe tomography (APT) were…
The status of research and development on vanadium alloys and on their application as a structural material in the breeder blanket of a fusion power plant are reviewed. Emphasis has been placed on irradiation experiments and the effects of neutron and ion irradiation on the microstructure of the current reference alloy, V-4Cr-4Ti. The effects of a …
