Oxide dispersion strengthened (ODS) alloys are characterized by nanoscale oxide particles
homogeneously dispersed in a metallic matrix. They have been developed driven by …

Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …

Generation IV nuclear power plants (GEN IV NPPs) are supposed to become, in many
countries, an important source of base load power in the middle–long term (2030–2050) …

Reduced activation ferritic/martensitic steels are currently the most technologically mature
option for the structural material of proposed fusion energy reactors. Advanced next …

Tungsten materials are candidates for plasma-facing components for the International
Thermonuclear Experimental Reactor and the DEMOnstration power plant because of their …

The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …

This article summarizes the recent progress on developing a class of potentially
transformational structural materials called nanostructured ferritic alloys, which are leading …

The intricate balance between reactor economics and safety necessitates the emergence of
new and advanced nuclear systems and, very importantly, advanced materials, which can …

The nanoparticles in an Al-alloyed high-Cr oxide dispersion strengthened (ODS) steel with
Zr addition, ie, SOC-14 (Fe–15Cr–2W–0.1 Ti–4Al–0.63 Zr–0.35 Y 2 O 3), have been …

FeCrAl oxide dispersion strengthened (ODS) steel is one of the most promising candidate
cladding materials for Generation IV nuclear reactors due to its superior high temperature …