Add to ORKGThis paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering
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 ...
International audienceCorrosion and material sciences face challenges which involved and still need ...
Today more than 400 light water power reactors (LWRs) operate worldwide providing approximately 17% ...
The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corros...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
In the post-Fukushima world, thermal and structural stability of materials under extreme conditions ...
International audienceIn PWR, the Zircaloy based clad is the first safety barrier of the fuel rod, i...
Thesis (Nucl. E. and S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 200...
In PWR plants, nuclear fuel pellets (cylinders 1.2 cm length, 0.84 cm diameter) are piled in nuclea...
Zirconium alloys are used in key components in nuclear reactors, e.g. fuel cladding tubes in pressur...
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 ...
International audienceCorrosion and material sciences face challenges which involved and still need ...
Today more than 400 light water power reactors (LWRs) operate worldwide providing approximately 17% ...
The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corros...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
In the development of zirconium alloys for nuclear service, one of the main tasks has been to improv...
In the post-Fukushima world, thermal and structural stability of materials under extreme conditions ...
International audienceIn PWR, the Zircaloy based clad is the first safety barrier of the fuel rod, i...
Thesis (Nucl. E. and S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 200...
In PWR plants, nuclear fuel pellets (cylinders 1.2 cm length, 0.84 cm diameter) are piled in nuclea...
Zirconium alloys are used in key components in nuclear reactors, e.g. fuel cladding tubes in pressur...
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 ...
International audienceCorrosion and material sciences face challenges which involved and still need ...