|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||In situ EBSD Studies of Blocky Grain Growth in Welded Zircaloy-4
||Thomas Benjamin Britton, Ruth Birch
|On-Site Speaker (Planned)
||Thomas Benjamin Britton
Zirconium alloys, like Zircaloy-4, are popular nuclear fuel cladding materials due to their low thermal neutron absorption cross section, good mechanical performance, and that components can be manufactured using welding. Their performance is often enhanced through thermomechanical processing optimise microstructure. In welding, the microstructure can be adjusted due to local fusion, generation of residual stress and plastic work. In this study, we employ in situ electron backscatter diffraction (EBSD) observations with heating to explore zircaloy-4 microstructure and the formation of very large 'blocky' alpha grain growth (grain size >500 μm) for electron beam welds. Using parent grain reconstruction, we reveal that the while the prior beta grain structure is important in the evolution of the microstructure but that the crystallographic texture, grain shape and grain structure is nucleation controlled. These findings are important when designing and improving the manufacturing routes of multipart zirconium components.