In the development of zirconium alloys for nuclear service, one of the main tasks has been to improve the corrosion properties. Subsequently the corrosion of zirconium alloys has been studied extensively since the beginning of the commercial nuclear era, resulting in numerous reports and articles. The aim of this work has been to review the recent trends in opinions on the corrosion mechanisms, the trends in alloy development, and the in-reactor experience gained up till now. Some of the properties of the zirconium oxide film have also been given, the properties can be used as input data in corrosion models. Among zirconium alloys, mainly Zircaloy-2, Zircaloy-4, Zr-l%Nb and Zr-2.5%Nb, the only alloys of commercial importance in nuclear serv...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
Evaluation of integrity and corrosion mechanism of primary circuit materials is one of the main fact...
Corrosion properties of Zr-Sn and Zr-Nb zirconium alloys were studied under simulated PWR conditions...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
The present thesis focus on the corrosion mechanism of new zircaloys, those Zr-rich alloys more rece...
The present thesis focus on the corrosion mechanism of new zircaloys, those Zr-rich alloys more rece...
The development of zirconium and its alloys for use in nuclear reactors began in the United States ...
This paper describes the historical development of zirconium and its alloys as structural materials ...
A program was initiated for the design of steam-service Zr base cladding alloy. Specifications were ...
Zirconium alloys are used in key components in nuclear reactors, e.g. fuel cladding tubes in pressur...
This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrica...
On the basis of 4800 hr exposure to 680 l F water, a number of ternary compositions were shown to ha...
Zirconium alloys are routinely used as cladding material in the nuclear industry due to the favorabl...
Zirconium and its alloys are considered as candidate materials for various applications in spent nuc...
The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corros...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
Evaluation of integrity and corrosion mechanism of primary circuit materials is one of the main fact...
Corrosion properties of Zr-Sn and Zr-Nb zirconium alloys were studied under simulated PWR conditions...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
The present thesis focus on the corrosion mechanism of new zircaloys, those Zr-rich alloys more rece...
The present thesis focus on the corrosion mechanism of new zircaloys, those Zr-rich alloys more rece...
The development of zirconium and its alloys for use in nuclear reactors began in the United States ...
This paper describes the historical development of zirconium and its alloys as structural materials ...
A program was initiated for the design of steam-service Zr base cladding alloy. Specifications were ...
Zirconium alloys are used in key components in nuclear reactors, e.g. fuel cladding tubes in pressur...
This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrica...
On the basis of 4800 hr exposure to 680 l F water, a number of ternary compositions were shown to ha...
Zirconium alloys are routinely used as cladding material in the nuclear industry due to the favorabl...
Zirconium and its alloys are considered as candidate materials for various applications in spent nuc...
The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corros...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
Evaluation of integrity and corrosion mechanism of primary circuit materials is one of the main fact...
Corrosion properties of Zr-Sn and Zr-Nb zirconium alloys were studied under simulated PWR conditions...