About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Effect of Cr Coating Thickness on the Oxidation Resistance of Coated Zircaloy-4 for Accident Tolerant Fuel Cladding and the Effect of Hydride Formation |
| Author(s) |
Brock Nowak, You Wu, Kevin Daub, Suraj Persaud, Zhongwen Yao |
| On-Site Speaker (Planned) |
Brock Nowak |
| Abstract Scope |
This study looks at two critical areas of interest: (i) the effect of Cr coating thickness on high-temperature oxidation resistance, and (ii) investigation into the formation of hydrides in coated cladding. Coatings were deposited on Zircaloy-4 cladding (h = 400 µm, CANDU®) via magnetron sputtering at 381 °C (0.3 Tm,Cr), 5 mTorr, and -60 V substrate bias for 5-20 h depending on the desired thickness (1 h ≈ 1 µm). High-temperature steam oxidation tests were performed in an alumina tube furnace at 1130 °C for 180 to 14400 s for characterization of mass gain and microstructural evolution (SEM, EDS, XRD). Thermogravimetric analysis (TGA) was performed at 1130 °C, 1165 °C, and 1230 °C for 2 hours. Results indicate an optimal Cr coating thickness between 10-15 µm, considering oxidation resistance versus equivalent neutron cross section. Following this, gaseous charging and thermal cycling was performed to evaluate hydride effects in coated Zircaloy-4. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, High-Temperature Materials |