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 …

The present work reports the creep behaviour of a high yttria Fe-18Cr-2W-0.57 Ti-1Y 2 O 3
(all compositions in wt.%) ferritic oxide dispersion strengthened (ODS) steel produced by …

Oxide dispersion strengthened (ODS) Eurofer steel was prepared via mechanical alloying
(MA) and spark plasma sintering (SPS). Different combinations of MA and SPS parameters …

Abstract Ferritic/martensitic (F/M) steels are promised candidate materials for the lead-
cooled fast neutron reactor. However, their poor high temperature performance limits the …

To access irradiation conditions of candidate materials used in advanced nuclear energy
systems, simultaneous helium and iron-ion irradiation have been widely used to study on …

Irradiation hardening caused by helium (He) ion bombardment is directly related to the
pinning effect of He-related defects on dislocation glide in metals. Taking tungsten as an …

Plasma facing materials (PFMs) face one of the most serious challenges in fusion reactors,
including unprecedented harsh environment such as 14.1 MeV neutron and transmutation …

The irradiation damage behavior was studied in the Selective laser melted (SLM) 304L
stainless steel irradiated by 5 MeV Xe ions at room temperature. The changes in the …

In future fusion reactors, the production and accumulation of helium (He) will lead to a
dramatic mechanical failure for the material. Tungsten (W) is considered as one of the most …

The creep properties, microstructural evolution, and fracture mechanism of 16Cr-3Al oxide
dispersion strengthened (ODS) steel were systematically investigated at 600° C under …