Pure tungsten samples have been neutron irradiated in HFIR at 90–850° C to 0.03–2.2 dpa.
A dispersed barrier hardening model informed by the available microstructure data has …

Estimations of bulk hardness from nanoindentation are frequently subject to considerable
uncertainties due to indentation size effects (ISE), pileup effects, and potential influence of …

Additively manufactured (AM) 316 L stainless steel (SS) after hot isostatic pressing (HIP)
was found to exhibit superior resistance to irradiation-assisted stress corrosion cracking …

International development of reduced activation ferritic-martensitic (RAFM) steels has
focused on 9 wt percentage Cr, which primarily contain M 23 C 6 (M= Cr-rich) and small …

The poor machinability and extensive work hardening of Ni-based superalloys makes
additive manufacturing an attractive option for producing geometrically complex components …

Post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF)
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …

Co-free but Al-included medium/high entropy alloys (M/HEAs) have gained increasing
interests due to their lower cost and the potential to tune the multi-phase microstructure. The …

In this study, we demonstrate the methodology systematically developed for dislocation loop
(perfect and faulted loops) imaging and analysis in irradiated face-centered-cubic (FCC) …

Ferritic/martensitic steels T91 and HT9 were irradiated with neutrons (BOR-60 reactor) and
dual ions (9 MeV Fe 3+ and 3.42 MeV energy degraded He 2+) from 369 to 520° C and …

High/medium entropy alloys (HEAs/MEAs) are good candidates for nuclear applications due
to the excellent mechanical properties, good corrosion resistance and radiation resistance …