|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Interconnectivity Quantification and Corrosion Mechanisms in Zr Alloys
||Hongliang Zhang, William Howland, Adrien Couet
|On-Site Speaker (Planned)
As cladding materials in PWR, Zr alloys will be corroded in high temperature and pressure water, forming the oxide layer. Pores and cracks are widely found in the formed oxide. A current hypothesis is that ingress of the oxidizing species results from connected oxide nano-porosity and that oxide protective properties are lost when this porosity interconnects down to the oxide/metal interface. In addition, the variation in substrate texture is known to result in lattice-match vs. stress-driven oxide growth modes. To examine the hypothesis and explore the detailed oxidation mechanisms, pores were firstly imaged, and 3D reconstructed to study interconnectivity and shortest path. Zr alloys were also corroded in 18O riched pressurized liquid water at 360°C. In-situ TEM and APT are used to study the oxidation mechanisms, as well as the detailed compositions of the oxide grains and nano-porosities (either intra-granular or inter-granular.
||Nuclear Materials, Environmental Effects, Machine Learning