Abstract
In water-cooled nuclear power reactors, zirconium alloys as fuel cladding are important structural materials. Many factors will lead to the failure of the zirconium alloy cladding, and the corrosion resistance is the most important factor that affects the service life of the fuel element. E110 (Zr-1Nb, wt.%) and M5 (Zr-1Nb-0.16O) alloys are typical Zr-Nb series zirconium alloys used in commercial reactors. It is well-known that most of second phase particles are β-Nb in Zr-Nb series alloys, and many researchers believe that the corrosion resistance of Zr-Nb alloy is related to the oxidation process of β-Nb precipitates. Due to its size limitations, it is difficult to conduct in-depth and systematic research on the oxidation process of β-Nb precipitates. Therefore, we prepared the 90Nb-10Zr binary alloy with the same microstructure and composition of β-Nb and investigated its oxide characteristics in different water chemical environments. The corrosion products of 90Nb-10Zr alloy vary with the corrosion environments. Based on the transmission electron microscopy observation results of corrosion products formed on the 90Nb-10Zr alloy, a hypothesis of corrosion acceleration of Zr-1Nb alloy in lithiated water is proposed from the perspective of β-Nb SPPs oxidation.
Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
