From the irradiation resistance and high-temperature strength, oxide dispersion
strengthened (ODS) ferritic steels are candidate materials for advanced and fusion reactors …

Oxide dispersion strengthened (ODS) ferritic steels are candidates for cladding tubes in fast
breeder nuclear reactors. In this study, an 18% Cr ODS ferritic steel was prepared through …

ODS ferritic steels (13Cr–0.5 Ti–0.2 Y2O3) were prepared by the mechanical alloying
method followed by the hot extrusion and several heat treatments including recrystallization …

12Cr ferritic ODS steel was fabricated by mechanical alloying (MA), hot isostatic pressing
(HIP) and hot rolling processes. Thermal stability of the oxide particles in the ODS steel …

A 14Cr-ODS ferritic steel with the nominal compositions of Fe–14Cr–2 W–0.3 Ti–0.3 Y 2 O 3
(wt.%) was produced by mechanical alloying (MA) and hot isostatic pressing (HIP). Helium …

Excellent high-temperature strength and resistance to radiation damage of 9Cr Oxide
Dispersion Strengthened (9Cr-ODS) martensitic steel have been realized by nano-size Y–Ti …

In order to develop a robust alumina scale dispersed with nano-oxide particles for FeCrAl
oxide dispersion strengthened (ODS) ferritic alloys, the oxidation behavior of FeCrAl ODS …

Oxide dispersion strengthened (ODS) steels are the most fascinating candidate materials for
high temperature nuclear applications. ODS steel with nominal composition of Fe–14Cr–2W …

FeCrAl oxide dispersion strengthened (ODS) steel is regarded as one of the most promising
candidate materials for nuclear fission reactors such as supercritical pressurized water …

Two ODS ferritic steels with nominal compositions (wt.%): Fe–14Cr–0.3 Y 2 O 3 and Fe–
14Cr–2W–0.3 Ti–0.3 Y 2 O 3 have been produced by mechanical alloying and consolidation …