| About this Abstract |
| Meeting |
2016 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Fuels for the Current and Advanced Nuclear Reactors V
|
| Presentation Title |
Al-Ti-Cr Coating on Zr Alloys for Enhancing Accident Tolerance of Fuel Claddings |
| Author(s) |
Jeong-Yong Park, Il-Hyun Kim, Hyun-Gil Kim, Yang-Il Jung, Dong-Jun Park, Jung-Hwan Park, Yang-Hyun Koo |
| On-Site Speaker (Planned) |
Jeong-Yong Park |
| Abstract Scope |
Surface coating on Zr fuel cladding is one of the options to improve the oxidation resistance of fuel claddings. Intermetallic compounds in Al-Ti-Cr system were proposed as the candidate coating materials that contribute to enhancement of the accident tolerance of nuclear fuel. The oxidation test under accident conditions (1200 oC steam) showed that Al-Ti-Cr alloys exhibited an extremely low oxidation rate with stable Al2O3 on the surface. The corrosion behavior of Al-Ti-Cr alloys under normal reactor operation condition (360 oC water) was very sensitive to the environments. Al-Ti-Cr alloys were coated on Zr alloys using a direct laser deposition. The coated specimens were subjected to the high temperature oxidation test. The coated layer was effective to prevent Zr alloys from being severely oxidized. The oxidation resistance of the coated Zr alloys was significantly different depending on the coating layer protectiveness that was highly affected by the coating condition. |
| Proceedings Inclusion? |
Planned: A print-only volume |