Title: Design of Al-containing High-Cr ODS Ferritic Steels for Nuclear Energy Systems

Speaker: Prof. Akihiko Kimura

Time: 9:30-10:30, May. 21 (Wednesday), 2025

Place: Room 911, Building 5 

Abstract: 

High performance structural materials R&D is essential for the realization of advanced nuclear fission and fusion energy systems. 9Cr-ODS martensitic steel was developed as a cladding material for sodium-cooled first breeder reactor in Japan, and the steel showed a good performance in sodium, while its corrosion resistance is poor in supercritical water (SCW) and lead-bismuth eutectics (LBE).

High-Cr ODS ferritic steels added with Al showed a drastic improvement in the corrosion resistance in SCW and LBE. High-temperature strength, however, was reduced by Al addition because of the characteristic changes in the dispersion morphology of oxide particles. Finally, we developed "Super ODS steels" with a small addition of Zr, which results in the improvement of high-temperature strength with maintaining high-resistance to corrosion in SCW and LBE.