FeCrAl alloys exhibit outstanding high-temperature oxidation resistance and impressive
mechanical strength, rendering them as forefront materials with broad applicability across …

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 …

Three model ODS alloys (Fe–0.3 Y 2 O 3, Fe–0.2 Ti–0.3 Y 2 O 3 and Fe–14Cr–0.2 Ti–0.3 Y
2 O 3) were prepared by ball milling and then hot extrusion to study the effect of Ti and Cr on …

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 …

Oxide dispersion strengthened (ODS) steels containing yttria are candidate materials for fuel
cladding tubes in future nuclear reactors. Their performance is determined by the size …

To study the effects of zirconium (Zr) addition on the microstructure, hardness and the tensile
properties of oxide dispersion strengthened (ODS) ferritic–martensitic steels, two kinds of …

Abstract Ferritic Oxides Dispersion Strengthened (ODS) steels are of great interest for
nuclear fission and fusion power plants. The nano-oxides embedded into the matrix provide …

Abstract Oxide Dispersion Strengthened (ODS) steels are candidates for nuclear
applications. ODS are produced by mechanical alloying of Fe-14Cr, Y 2 O 3 and TiH 2 …

In this paper, the effects of hafnium (Hf) addition on the thermal stability of the microstructure
and tensile properties of Al-containing 16Cr-ODS steels were investigated. High …

The ODS ferritic/martensitic (ODS-FM) steel was irradiated up to 500 dpa at 550° C with 2.5
MeV Fe 2+ ions to investigate the microstructure evolution under low to very high doses …