|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Characterizing and Modelling Precipitation in Zirconium Alloys
||Zaheen Shah, Joseph Robson, Michael Preuss, Magnus Limbäck, Mattias Alm
|On-Site Speaker (Planned)
Zirconium alloys are widely used in light water nuclear reactors as fuel cladding, the lifetime of which is limited by aqueous corrosion. The corrosion resistance of these alloys is influenced by the size, number density and distribution of second phase particles (SPPs), characteristics altered by changing chemical composition and various thermomechanical processing stages such as annealing. The evolution of SPPs at each processing stage is studied on Zircaloy-2 and the novel high-Fe alloy, HiFi™. SPP characterisation is performed using energy selective backscatter imaging in a field emission gun scanning electron microscope. Throughout processing, SPP size distributions shift to larger sizes in both alloys whilst HiFi generally has a higher particle number density than Zircaloy-2. The corresponding SPP data is used to validate a novel model developed to predict SPP precipitation and growth kinetics in zirconium alloys. This work enables optimisation of the processing route to further enhance in-reactor corrosion performance.
||Planned: Supplemental Proceedings volume