Oxide dispersion strengthened (ODS) alloys are characterized by nanoscale oxide particles
homogeneously dispersed in a metallic matrix. They have been developed driven by …

After the Fukushima nuclear accident, the development of new accident-tolerant fuel
cladding materials has become a research hotspot around the world. Due to its outstanding …

FeCrAl oxide dispersion strengthened (ODS) steel is one of the most promising candidate
cladding materials for Generation IV nuclear reactors due to its superior high temperature …

Oxide dispersion strengthened (ODS) FeCrAl alloys have been considered as the promising
candidate fuel cladding materials for the Gen-IV fission reactors due to excellent radiation …

FeCrAl oxide dispersion strengthened (ODS) steel is one of the most promising candidate
cladding materials of generation IV nuclear reactors because of its excellent resistance to …

Oxide dispersion strengthened (ODS) Ni-based superalloys with high Al and Ti content (Ni–
20Cr-xAl-yTi-0.6 Y 2 O 3-0.6 Zr, x/y=∼ 1, 1.8 and 16, named ST, SAT and SA alloy …

Oxide dispersion strengthened (ODS) high entropy alloys (HEAs) are potential structural
materials for advanced nuclear reactor application due to their excellent radiation tolerance …

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 …

Oxide dispersion strengthened (ODS) Fe-12Cr-5Al-2 W-xZr (x= 0, 0.3, 0.6, 1.0 wt%) alloys
were produced by mechanically alloying and spark plasma sintering. The size and …

Oxide dispersion strengthened (ODS) steel is one of the most promising candidate structural
materials for the high-temperature nuclear reactor application. In this study, two …