The oxidation of zirconium alloys is one of the most studied processes in the nuclear industry. The purpose of this report is to provide in a concise form a review of the oxidation process of zirconium alloys in the moderate temperature regime. In the initial ''pre-transition'' phase, the surface oxide is dense and protective. After the oxide layer has grown to a thickness of 2 to 3 {micro}m's, the oxidation process enters the ''post-transition'' phase where the density of the layer decreases and becomes less protective. A compilation of relevant data suggests a single expression can be used to describe the post-transition oxidation rate of most zirconium alloys during exposure to oxygen, air, or water vapor. That expression is: Oxidation R...
In these days, many types of researches have been performed to enhance the oxidation resistance of a...
U3O8; kinetics; oxygen partial pressure; pseudo steady state; rate-limiting step. The oxidation by w...
cited By 35Progress in the treatment of air oxidation of zirconium in severe accident (SA) codes are...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
The oxidation of zirconium and several zirconium alloys was investigated in the temperature range 40...
Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...
Zirconium is one of those few metals which are capable of dissolving relativelylarge quantities of o...
The rate of oxidation of a zirconium 1.5 wt % tin alloy followed a cubic law in the temperature rang...
AbstractAs a cladding material used to encapsulate nuclear fuel pellets, zirconium alloys are the pr...
Zirconium based alloys (and particularly Zircaloy-4) are widely used as cladding material of fuel ro...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
1. Introduction2. State of the Art2.1 Materials and their Thermodynamic Properties2.2 Growth Mechani...
In these days, many types of researches have been performed to enhance the oxidation resistance of a...
U3O8; kinetics; oxygen partial pressure; pseudo steady state; rate-limiting step. The oxidation by w...
cited By 35Progress in the treatment of air oxidation of zirconium in severe accident (SA) codes are...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
The oxidation of zirconium and several zirconium alloys was investigated in the temperature range 40...
Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...
Zirconium is one of those few metals which are capable of dissolving relativelylarge quantities of o...
The rate of oxidation of a zirconium 1.5 wt % tin alloy followed a cubic law in the temperature rang...
AbstractAs a cladding material used to encapsulate nuclear fuel pellets, zirconium alloys are the pr...
Zirconium based alloys (and particularly Zircaloy-4) are widely used as cladding material of fuel ro...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
1. Introduction2. State of the Art2.1 Materials and their Thermodynamic Properties2.2 Growth Mechani...
In these days, many types of researches have been performed to enhance the oxidation resistance of a...
U3O8; kinetics; oxygen partial pressure; pseudo steady state; rate-limiting step. The oxidation by w...
cited By 35Progress in the treatment of air oxidation of zirconium in severe accident (SA) codes are...