Neutron irradiation poses a substantial challenge in the development and application of
tungsten (W) and its alloys, predominantly in the framework of nuclear fusion and fission …

Material test reactors (MTRs) are used to irradiate nuclear fuels and materials to develop
data for how they endure neutron bombardment in or near reactor cores. Most historic MTRs …

Ductile-to-brittle transition (DBT) is frequently found in bcc W-based alloy systems, leading to
varied fracture toughness at different temperatures. Re is recognized as an effective alloying …

A novel high-strength conductive Cu-based composite, utilizing AlCrCuFeNi 2.5 (Ni2. 5)
high-entropy alloy particles as the reinforcing phase, is synthesized through a combination …

Post irradiation examination of two commercial tantalum alloys (based on Ta-8% W)
revealed significant irradiation hardening following neutron irradiation in the High Flux …

Gaining insight into the underlying mechanisms driving nanoindentation-induced behavior
in tungsten is essential for comprehending its mechanical properties. Although the plasticity …

M. Worrall et al. recently published a manuscript titled “Fast neutron irradiation capability in
existing thermal test reactors”(Worrall, 2024) that summarizes an irradiation vehicle design …

High strength, high conductivity copper alloys that can resist creep at high temperatures are
one of the primary candidates for efficient heat exchangers in fusion reactors. Cu–Cr–Nb–Zr …