| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Late News Poster Session
|
| Presentation Title |
N-46: ZrO2 Corrosion Layers and Their Grain Boundary Networks |
| Author(s) |
Aaron Chote |
| On-Site Speaker (Planned) |
Aaron Chote |
| Abstract Scope |
Zircaloy-4 is the principal alloy employed as the cladding material in the UK’s only pressurised water reactor (PWR). Lithium is an additive in the coolant water of PWRs but the effect of lithium on the microstructural evolution and texture of the growing ZrO2 layer is not well-understood. Lithiated and non-lithiated ZrO2 layers from autoclaved Zircaloy 4 samples (oxidised for 105 days at 573K, 140MPa in 70-ppm lithiated water) were probed using precession electron diffraction, providing insight into the grain boundary plane distribution and grain boundary character distribution. Atom probe tomography was used to understand lithium’s segregation behaviour in ZrO2 layers. A change in thickness of the ZrO2 layer related to the underlying Zircaloy-4 grain orientation was observed, along with the co-segregation of lithium and iron to grain boundaries. The effect that lithium has on the prominence of certain grain boundary planes and the texture evolution in ZrO2 layers is discussed. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
Characterization, Nuclear Materials, |