| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
|
| Presentation Title |
Thermal Response and Mechanical Integrity of High Temperature Cr-Coated Zr Cladding Under Multiple Quench Tests |
| Author(s) |
WooHyun Jung, Cole Dunbar, Jun Yeong Jo, Kumar Sridharan, Hwasung Yeom |
| On-Site Speaker (Planned) |
Hwasung Yeom |
| Abstract Scope |
Cr-coated Zr-alloy cladding designs are most promising Accident Tolerant Fuel (ATF) cladding in LWR by virtue of excellent corrosion and oxidation resistance under high temperature accident conditions. Multiple reflood experiments for the coated cladding were performed to evaluate thermal response and mechanical integrity under severe thermal transient conditions such as load-following scenario and loss-of-coolant accident, which were then compared with uncoated cladding. The coated cladding exhibited high precision quench temperatures, heat transfer transition points in quenching, whereas the uncoated cladding showed increased (and scattered) quench temperatures as repeating the tests up to 1100 °C. Loss of mechanical integrity of the uncoated samples was observed in the quenched several times at high temperatures, while the coated samples under the sample condition remained intact. The results demonstrate that the coated cladding would provide improved integrity and performance under a wide range of power transient conditions in LWRs. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Powder Materials |