Abstract
Oxide dispersion-strengthened (ODS) steels are main candidates for structural applications in future fusion reactors. Understanding their irradiation-induced behaviour is a key in building optimised components with enhanced radiation resistance. In this work, the stability of an ODS Fe12Cr steel was investigated by transmission electron microscopy after single- (Fe4+) and simultaneous triple-ion-beam irradiation (Fe8+, He+ and H+) at room temperature to doses of 4.4 and 10 dpa. The irradiations were accomplished at the JANNUS-Saclay facility. Results after single-ion-beam irradiation were also compared with those from a reference Fe12Cr steel produced following the same route. Analyses focused on determining the irradiation-induced loop size and density in the ODS and reference materials, investigating the grain boundary microchemistry and studying the evolution of the secondary phases present. These experiments show that the Y-rich nanoparticles present in the ODS steel are quite stable under these irradiation conditions although evolution of larger Cr-rich carbides could be taking place. Loop sizes are smaller for the ODS steel than for the reference material and appear to increase with dose. Cr segregates at some of the grain boundaries, though this segregation also occurs in the absence of irradiation.
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