Oxide dispersion strengthened (ODS) ferritic steel is a potential structural material for fast
neutron reactor and fusion reactor application. In this study, a new Fe–13Cr–2W-0.4 Ti-0.6 …

As a future material for a fusion first wall, ferritic steels have come to appear more attractive
than austenitic steels for their higher swelling resistance. To reduce the degradation in …

Ferritic steels strengthened with Ti–Y–O nanoclusters are leading candidates for fission and
fusion reactor components. A Fe–14Cr–0.4 Ti+ 0.25 Y 2 O 3 (14YT) alloy was fabricated by …

This paper discusses the effects of small amount of Al contamination (< 0.1 wt%) on high-
temperature strength and microstructure of the 9Cr–ODS steel. Increasing Al concentration …

Microstructural observation was performed on a neutron-irradiated oxide dispersion
strengthened (ODS) ferritic steel with emphasis on oxide behavior, including phase stability …

Oxide Dispersion Strengthened ferritic/martensitic steels are developed as future cladding
materials for Generation IV Sodium-Cooled Fast Reactors. ODS alloys are elaborated by …

An oxide dispersion strengthened ferritic-martensitic steel with yttrium oxide (Y2O3) was
produced by mechanical alloying and hot isostatic pressing techniques for high …

Oxide dispersion-strengthened ferritic steels were irradiated by neutrons up to 21 dpa and
studied by microstructural observation and microchemical analysis. The original high …

As prospective cladding material for the long-life core of a Fast Breeder Reactor (FBR), we
developed oxide dispersion strengthened (ODS) ferritic/martensitic steels, which have more …

Oxide Dispersion Strengthened (ODS) steels are promising candidate materials for fission
and fusion applications thanks to their improved properties related to both their fine grained …