Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …

Materials capable of sustaining high radiation doses at a high temperature are required for
next-generation fission and future fusion energy. To date, however, even the most promising …

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 …

In this work, we employ transmission electron microscopy and helium ion irradiation to study
the interactions between the radiation-induced point defects and the incoherent/semi …

As a candidate material for fuel cladding in fission reactors, the mechanical properties of
ODS-Ferritic/martensitic (F/M) steel should be further improved. Incorporating oxide …

The cold-rolling process yields a staggered dual-phase structure in the AlCoCrFeNi 2.1
eutectic high-entropy alloy (EHEA), showcasing resilience against high-temperature and …

Abstract Simultaneous Fe+ He ion irradiations of China Low Activation Martensitic (CLAM)
steel and oxide-dispersion-strengthened ferritic/martensitic (ODS-F/M) steel were carried out …

Oxide dispersion strengthened (ODS) steels, traditionally fabricated by ball milling and
conventional powder metallurgy techniques to achieve bulk form, followed by intricate rolling …

Nanocrystalline materials are known to possess excellent radiation resistance due to high
fraction of grain boundaries that act as defect sinks, provided they are microstructurally …

The objective of this study is to evaluate the influence of dose rate and cascade morphology
on nanocluster evolution in a model Fe-9% Cr oxide dispersion strengthened steel and the …