activity
20192026
most citedProton Irradiation-Decelerated Intergranular Corrosion of Ni-Cr Alloys in Molten Salt

99 citations · 314 across the 13 of their papers we have counts for

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Showing cond-mat.mtrl-sciShow all

9 papers · 1 filter

cond-mat.mtrl-sci2026

Anomalous bulk dealloying below the parting limit

Weiyue Zhou, Hooman Gholamzadeh, Lei Ding +9

Dealloying has been extensively studied both as a corrosion degradation mechanism in structural materials, including those used in nuclear, aerospace, or marine environments, and a…

cond-mat.mtrl-sci2026

Real-time vacancy concentration evolution revealed via heavy ion irradiation experiments

Elena Botica-Artalejo, Gregory Wallace, Michael P. Short

We show that in situ ion irradiation transient grating spectroscopy (I3TGS) can be used to monitor the real-time evolution of vacancy concentration generated by self-ion radiation…

cond-mat.mtrl-sci2026

Fragmenting Diffusion Pathways Confers Extraordinary Radiation Resistance in Refractory Multicomponent Alloys

Bin Xing, Bijun Xie, Wanjuan Zou +11

The accumulation and growth of vacancy clusters under irradiation is a pivotal degradation mode for structural materials in extreme environments. Even tungsten undergoes rapid defe…

cond-mat.mtrl-sci2026

Rapid Primary Radiation Damage Resistance Assessment of Precipitation-Hardened Cu Alloys

Elena Botica-Artalejo, Gregory Wallace, Michael P. Short

This study establishes a direct correlation between in situ irradiation-induced property changes measured by transient grating spectroscopy (TGS) and the resulting microstructural…

cond-mat.mtrl-sci2026

Corrosion Evolution of T91 Steel in Static Lead-Bismuth Eutectic Under an Oxidising Environment

Minyi Zhang, Weiyue Zhou, Michael P. Short +3

Understanding corrosion in liquid metal-cooled nuclear systems is essential in order be able to control it. While much literature exists detailing corrosion rates and mechanisms of…

cond-mat.mtrl-sci2023★ 19 cited

Characterisation of Corrosion Damage in T91/F91 steel exposed to Liquid Lead-Bismuth Eutectic

M. T. Lapington, M. Zhang, M. P. Moody +3

T91 samples were exposed to static liquid lead-bismuth eutectic (LBE) at 700°C for 250-500 hours in either an oxidising or reducing environment. Corrosion damage was characterised…