International audienceA new experimental thermogravimetric device has been installed to study in situ the corrosion behaviour of zirconium alloys under high pressure of steam. Corrosion tests up to 5 MPa of steam pressure have been performed on two materials, pure zirconium and Zircaloy-4 (Zy4), at around 415 degrees C. The rate-limiting step assumption was experimentally verified on Zy4. Unlike pure zirconium, its oxidation rate is not dependent on steam pressure. The experimental result obtained on this material is consistent with an oxygen vacancy diffusion rate-limiting step. For pure zirconium, the kinetic law is nearly linear during the corrosion process, which leads to propose an interface reaction rate-limiting step. Moreover, accor...
International audienceZircaloy-4 (Zy-4) cladding, the first containment of UO2 fuel in Pressurized W...
International audienceThe oxidation by water vapour of a zirconium based alloy, a ZrNbO alloy contai...
1. Introduction2. State of the Art2.1 Materials and their Thermodynamic Properties2.2 Growth Mechani...
International audienceA new experimental thermogravimetric device has been installed to study in sit...
A series of scoping tests to determine the influence of steam pressure on the isothermal oxidation k...
International audienceThe kinetic behavior of Zircaloy-4 tube samples was examined during high tempe...
Oxidation rate data for Zircaloy-4 in steam under isothermal conditions in the temperature range 100...
International audienceZircaloy4 (Zy-4) cladding, providing the first containment barrier of UO2 fuel...
The effect of pre-oxidation i dry oxygen gas on the corrosion behavior of Zircaloy-2 and unalloyed z...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
Behavior of zirconium alloy clad UO{sub 2} fuel elements in steam and air at 100 deg C to the meltin...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
International audienceThe oxidation of chromium-coated zirconium-based alloys is studied under steam...
International audienceZircaloy-4 (Zy-4) cladding, the first containment of UO2 fuel in Pressurized W...
International audienceThe oxidation by water vapour of a zirconium based alloy, a ZrNbO alloy contai...
1. Introduction2. State of the Art2.1 Materials and their Thermodynamic Properties2.2 Growth Mechani...
International audienceA new experimental thermogravimetric device has been installed to study in sit...
A series of scoping tests to determine the influence of steam pressure on the isothermal oxidation k...
International audienceThe kinetic behavior of Zircaloy-4 tube samples was examined during high tempe...
Oxidation rate data for Zircaloy-4 in steam under isothermal conditions in the temperature range 100...
International audienceZircaloy4 (Zy-4) cladding, providing the first containment barrier of UO2 fuel...
The effect of pre-oxidation i dry oxygen gas on the corrosion behavior of Zircaloy-2 and unalloyed z...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
Behavior of zirconium alloy clad UO{sub 2} fuel elements in steam and air at 100 deg C to the meltin...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
International audienceThe oxidation of chromium-coated zirconium-based alloys is studied under steam...
International audienceZircaloy-4 (Zy-4) cladding, the first containment of UO2 fuel in Pressurized W...
International audienceThe oxidation by water vapour of a zirconium based alloy, a ZrNbO alloy contai...
1. Introduction2. State of the Art2.1 Materials and their Thermodynamic Properties2.2 Growth Mechani...