A detailed characterization of nanostructured thin zirconium oxide films formed during aqueous corrosion of a nuclear-grade zirconium alloy (Zircaloy-4) has been carried out by means of two novel, ultra-high-spatial-resolution grain mapping techniques, namely automated crystal orientation mapping in the transmission electron microscope (TEM) and transmission electron backscatter diffraction (t-EBSD). While the former provided excellent spatial resolution with the ability to identify tetragonal ZrO2 grains as small as ∼5 nm, the superior angular resolution and unambiguous indexing with t-EBSD enabled verification of the TEM observations. Both techniques revealed that in a stress-free condition (TEM foil prepared by focused ion beam milling),...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
Characterisation of materials utilised for fuel cladding in nuclear reactors prior to service is int...
A detailed characterization of nanostructured thin zirconium oxide films formed during aqueous corro...
AbstractA detailed characterization of nanostructured thin zirconium oxide films formed during aqueo...
AbstractThe development of oxide texture and microstructure formed on two zirconium alloys with diff...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
AbstractDuring corrosion of zirconium alloys a highly textured oxide is formed, the degree of this p...
AbstractThe development of oxide texture and microstructure formed on two zirconium alloys with diff...
AbstractCharacterisation of materials utilised for fuel cladding in nuclear reactors prior to servic...
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 ...
Corrosion of zirconium fuel cladding is known to limit the lifetime and reloading cycles of fuel in ...
We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
Characterisation of materials utilised for fuel cladding in nuclear reactors prior to service is int...
A detailed characterization of nanostructured thin zirconium oxide films formed during aqueous corro...
AbstractA detailed characterization of nanostructured thin zirconium oxide films formed during aqueo...
AbstractThe development of oxide texture and microstructure formed on two zirconium alloys with diff...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
Understanding the key corrosion mechanisms in a light water reactor primary water environment is cri...
AbstractDuring corrosion of zirconium alloys a highly textured oxide is formed, the degree of this p...
AbstractThe development of oxide texture and microstructure formed on two zirconium alloys with diff...
AbstractCharacterisation of materials utilised for fuel cladding in nuclear reactors prior to servic...
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 ...
Corrosion of zirconium fuel cladding is known to limit the lifetime and reloading cycles of fuel in ...
We used a range of advanced microscopy techniques to study the microstructure, nanoscale chemistry, ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
Characterisation of materials utilised for fuel cladding in nuclear reactors prior to service is int...