Elevated temperature properties of ferritic/martensitic steels for application to future nuclear reators

The future nuclear systems such as nuclear hydrogen production reactors and fusion reactor require low activation and radiation embrittlement resistance in addition to excellent high temperature properties because their operating temperature are even higher than those of the light water reactors. The R and D of ferritic-martensitic steels in nuclear leading centuries like USA, Japan and EU has been continued for decades of years nuclear and they commercialized several steels. Korea consider modified 9Cr-1Mo steel as a candidate materials for reactor pressure vessel of very high temperature reactor. This state-of-the art report aimed to provide informations about the applicabilities of high Cr steels and low Cr steels through the analyses of their microstructures, mechanical properties and radiation characteristics. The metallurgical understanding of background of alloy evolutions might be helpful for the establishment of research orientation