Oxidized zirconium surfaces have been studied by X-ray photoelectron spectroscopy (XPS) and low-energy electron diffraction (LEED). The aim is to provide a fundamental understanding of the chemistry and structure of such surfaces as well as for metal-oxide interfaces; the motivation is to help establish understanding in relation to problems associated with nuclear reactor pressure tube corrosion. The chemistry of a thin film (-20 Å) of oxidized zirconium was studied by XPS. The film, prepared by depositing zirconium onto Au foil in the presence of a H₂0 atmosphere in the low 10⁻⁹ Torr range, has an outer region of Zr0₂and inner regions containing a lower oxidation state material, ZrOx, as well as Zr-Au alloy. Initially both ZrOx and the...
The trend towards increased fuel burn-up and higher operating temperatures in order to achieve more ...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
AbstractCharacterisation of materials utilised for fuel cladding in nuclear reactors prior to servic...
Oxidized zirconium surfaces have been studied by X-ray photoelectron spectroscopy (XPS) and low-ene...
The work in this thesis includes LEED crystallographic investigations for the (2x2) structure obtain...
Surface oxidation of pure zirconium and its dilute binary alloys with tin, chromium and iron has bee...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
Interactions of oxygen with Zr(0001) have been studied using low energy electron diffraction (LEED),...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years i...
Zirconium is one of those few metals which are capable of dissolving relatively large quantities of ...
Aqueous corrosion and hydrogenation have become major limiting factors to the use of zirconium alloy...
AbstractAn improved methodology of the Zr specimen preparation was developed which allows fabricatio...
The work in this thesis includes crystallographic investigations with low-energy electron diffractio...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
ABSTRACT: Ultrathin (∼3 Å) zirconium oxide films were grown on a single-crystalline Pt3Zr(0001) subs...
The trend towards increased fuel burn-up and higher operating temperatures in order to achieve more ...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
AbstractCharacterisation of materials utilised for fuel cladding in nuclear reactors prior to servic...
Oxidized zirconium surfaces have been studied by X-ray photoelectron spectroscopy (XPS) and low-ene...
The work in this thesis includes LEED crystallographic investigations for the (2x2) structure obtain...
Surface oxidation of pure zirconium and its dilute binary alloys with tin, chromium and iron has bee...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
Interactions of oxygen with Zr(0001) have been studied using low energy electron diffraction (LEED),...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years i...
Zirconium is one of those few metals which are capable of dissolving relatively large quantities of ...
Aqueous corrosion and hydrogenation have become major limiting factors to the use of zirconium alloy...
AbstractAn improved methodology of the Zr specimen preparation was developed which allows fabricatio...
The work in this thesis includes crystallographic investigations with low-energy electron diffractio...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
ABSTRACT: Ultrathin (∼3 Å) zirconium oxide films were grown on a single-crystalline Pt3Zr(0001) subs...
The trend towards increased fuel burn-up and higher operating temperatures in order to achieve more ...
Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns ...
AbstractCharacterisation of materials utilised for fuel cladding in nuclear reactors prior to servic...