HIGH TEMPERATURE TENSILE TEST OF 12Cr FERRITIC ODS STEEL

Oxide dispersion strengthened (ODS) steel is expected as high-performance structural components under heavy irradiations with neutrons at relatively high temperature in fusion reactors and advanced next generation fission reactors, like fast breeder reactors. In particular, the 12Cr ferritic ODS steel is regarded as one of the candidate structural materials for the reactors. In this study, mechanical properties of the alloy will be tested at different temperatures, and the effects of the microstructure will be investigated. Especially we will focus on the microstructural which is principally induced by the fabrication process of ODS steels. Fracture surface analysis at room temperature will be performed to clarify the fracture mechanism of this material.