The aim of this work is to investigate the effect of zirconium content on the mechanical
properties of ODS FeCrAl alloys, a kind of promising cladding materials for advance nuclear …

The influence of zirconium content on the microstructure of aluminum‐containing ODS
ferritic alloy was studied. Four kinds of 13Cr4Al ODS alloys with different Zr content between …

Abstract Low-chromium (< 10% Cr) high strength oxide dispersion strengthened (ODS)
FeCrAl alloys are considered promising candidates for accident tolerant fuel cladding in light …

A simple powder forging process was presented herein to fabricate an Fe-14Cr-4.5 Al-2W-
0.4 Ti-0.5 Y 2 O 3 ODS FeCrAl alloy. The forged alloy exhibits a high density that exceeds …

FeCrAl alloy with high Cr content is prone to generate a large number of α'phases under
irradiation condition at high temperature, which leads to hardening and embrittlement of the …

In order to meet the growing energy demand, more environmentally friendly and efficient
GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more …

FeCrAl alloy has great application potential to replace traditional zirconium alloy as an
accident-tolerant fuel (ATF) candidate material. In this study, Fe-13Cr-4Al-2Mo-0.65 Nb-0.4 …

FeCrAl-based steels are considered promising materials for high-temperature nuclear
applications. Over the past years, various compositions have been studied to assess their …

In light water reactors (LWR), it is necessary to decrease the thickness of the FeCrAl alloy
cladding to reduce neutron absorption to further reduce the impact on the reactor cycle …

Oxide dispersion strengthened ferritic steel is considered an important structural material in
fusion reactors due to its excellent resistance to radiation and oxidation. Fine and dispersed …