Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to analyse the structural and chemical properties of the metal-oxide interface of corroded Zr alloys in unprecedented detail. TEM, STEM and diffraction results revealed the complexity of the distribution of suboxide grains at the metal-oxide interface. EELS provided accurate quantitative analysis of the oxygen concentration across the interface, identifying the existence of local regions of stoichiometric ZrO and Zr3O2 with varying thickness. Transmission-EBSD confirmed that the suboxide grains can be indexed with the hexagonal ZrO structure predicted with ab initio by Nicholls et al. (2014). The t-EBSD analysis has also allowed for the mapping of a relatively larg...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to analyse the structur...
Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to analyse the structu...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
Zirconium alloys have been long used for fuel cladding and other structural components in water-cool...
Zirconium alloys have been long used for fuel cladding and other structural components in water-cool...
Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and ...
Zirconium alloys are widely used as structural and fuel cladding alloys in current nuclear pressuris...
Zirconium alloys are widely used as structural and fuel cladding alloys in current nuclear pressuris...
This work was produced as part of a multidisciplinary study of the corrosion of zirconium alloys und...
We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, ...
Aqueous corrosion and hydrogenation have become major limiting factors to the use of zirconium alloy...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to analyse the structur...
Here we report a methodology combining TEM, STEM, Transmission-EBSD and EELS to analyse the structu...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
Zirconium alloys have been long used for fuel cladding and other structural components in water-cool...
Zirconium alloys have been long used for fuel cladding and other structural components in water-cool...
Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and ...
Zirconium alloys are widely used as structural and fuel cladding alloys in current nuclear pressuris...
Zirconium alloys are widely used as structural and fuel cladding alloys in current nuclear pressuris...
This work was produced as part of a multidisciplinary study of the corrosion of zirconium alloys und...
We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, ...
Aqueous corrosion and hydrogenation have become major limiting factors to the use of zirconium alloy...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...