Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel
Cladding for Light Water Reactors (LWRs). Those materials are especially studied to …

Zirconium alloys are widely used in nuclear reactors as structural materials. During the
operation, they are exposed to fast neutrons. Ion irradiation is used to simulate the damage …

In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation
effects on the microstructure are first discussed, describing damage creation, point-defect …

Advancements in transmission electron microscopy allow us to draw correlations between
evolving matrix chemistry environments and the resulting dislocation structures that form …

Zirconium alloys are widely used structural materials of choice in the nuclear industry due to
their exceptional radiation and corrosion resistance. However long-time exposure to …

Zr-ion irradiation was performed on pure Zr, Zr-2.5 Nb, and Zr-5Nb to a dose of 0.5 or 5 dpa
at 573 K. The irradiation induced defects, alloying element redistribution, precipitation, and …

We investigate the effects of ion irradiation on AlGaN/GaN high electron mobility electron
transistors using in-situ transmission electron microscopy. The experiments are performed …

Irradiation induced growth is a constant volume shape change that occurs without externally
applied stress that is observed in some materials under irradiation damage. Proton …

A detailed study has been carried out on recrystallised Zr-1.0 Nb alloys corroded and
irradiated under different conditions, including ex-autoclave and ex-reactor samples. After …

The effect of Sn on the formation of-component dislocation loops was investigated by the
combination of in situ ion irradiation and density functional theory calculations. The size of …