| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Irradiation Effects on Zirconium Alloy Oxides and Their Impacts on In-reactor Corrosion Rates |
| Author(s) |
Adrien Couet, Zefeng Yu, Taeho Kim, Hongliang Zhang, Mukesh Bachhav, Lingfeng He |
| On-Site Speaker (Planned) |
Adrien Couet |
| Abstract Scope |
It is well-known that irradiation affects the in-reactor corrosion rates of zirconium alloy fuel cladding via irradiation effects in the substrate, the growing oxide and the water environment. In this study we will focus on the photon, neutron and ion irradiation effects in zirconium oxides. UV irradiation has been performed in-situ on zirconium alloys and the irradiated region shows a lower oxide thickness, and photo-electrochemically induced Fe oxide deposition. Proton and electron irradiation of zirconium oxides induces specific defects, likely F centers, characterized by Raman spectroscopy, which affect post-irradiation oxide growth. Finally, oxides grown in-reactor up to 4 cycles on ZIRLO®, M5® and X2® alloys have been characterized by STEM and APT to determine the effect of irradiation on the redistribution of alloying elements in the oxide. These observations are rationalized to propose an overall understanding of irradiation effects on zirconium oxide and their impacts on corrosion rate. |
| Proceedings Inclusion? |
Planned: |