| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Synergistic Irradiation, Corrosion, and Microstructural Evolution in Nuclear Materials
|
| Presentation Title |
Study of Irradiation Defects Annealing in Thermally Grown Oxides by In Situ Raman Spectroscopy |
| Author(s) |
Benoit Queylat, Taeho Kim, Adrien Couet |
| On-Site Speaker (Planned) |
Benoit Queylat |
| Abstract Scope |
In Pressurized Water Reactor, oxidation kinetics of zirconium alloys claddings is affected by irradiation of the oxide layer. In this environment, two phenomena dictate the oxide defect concentration evolution: creation by neutron irradiation and high-temperature annealing. While the impact of oxide irradiation on oxidation kinetics has been somewhat studied, there is very few data on defect annealing rate in PWR conditions. In this study, in situ Raman spectroscopy has been used to monitor irradiation defects annealing kinetics during corrosion. Two pre-oxidized zirconium alloys samples have been proton irradiated at temperature to simulate neutron irradiation effects in the oxide layer. The evolution of characteristic irradiation defects Raman bands has been monitored in-situ during subsequent corrosion tests in autoclave in high-temperature water, which allowed us to evaluate the annealing kinetics of irradiation induced defects in zirconia and its relation to oxidation kinetics. Other oxides relevant to nuclear materials are also examined. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Other |