The objective of this study is to evaluate the effect of irradiation on the strengthening
mechanisms of a model Fe-9% Cr oxide dispersion strengthened steel. The alloy was …

A model Fe–9% Cr oxide dispersion strengthened (ODS) steel was irradiated with protons or
neutrons to a dose of 3 displacements per atom (dpa) at a temperature of 500° C, enabling a …

The effects of neutron irradiation on the tensile properties of oxide dispersion strengthened
(ODS) ferritic steels have been investigated. Various ODS steels containing 14–22wt% Cr …

Oxide dispersion-strengthened (ODS) steels are main candidates for structural applications
in future fusion reactors. Understanding their irradiation-induced behaviour is a key in …

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

The objective of this study is to evaluate the effects of irradiation dose and dose rate on
defect cluster (ie dislocation loops and voids) evolution in a model Fe-9% Cr oxide …

The stability of MX-type precipitates is critical to retain mechanical properties of both
reduced activation ferritic–martensitic (RAFM) and conventional FM steels at elevated …

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

Understanding the behavior of oxide dispersion strengthened (ODS) ferritic/martensitic
steels under irradiation is vital in the design of advanced fusion reactors. In this work, a …

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 …