| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Burst Behavior of Accident Tolerant Fuel Cladding Concepts under Simulated Loss-of-coolant Conditions |
| Author(s) |
Samuel Bell, Bruce Pint, Ken Kane |
| On-Site Speaker (Planned) |
Samuel Bell |
| Abstract Scope |
Mitigating the dangers of a loss of coolant accident (LOCA) in a nuclear reactor has been a focus of the nuclear community since the 2011 Fukushima Daiichi disaster. Several accident tolerant alternatives have been proposed to address the oxidation related risks of the incumbent zirconium alloys, including replacement by ferritic iron-chromium-aluminum “FeCrAl” alloys or the application of a metallic oxidation resistant coating. Burst testing was conducted on first (T35Y2) and second (C26M) generation FeCrAl alloys, Zircaloy-2, Zirlo, and Cr coated zirconium claddings in a simulated LOCA environment. Mechanical characterization and general oxide analysis of all cladding concepts was conducted. Second generation FeCrAl showed tremendous improvements in burst strength compared to the other claddings. Cr coatings offered no improvement in burst strength of the underlying zirconium-based alloys but did significantly decrease oxide formation. This work was funded by the Advanced Fuels Campaign, Office of Nuclear Energy, U.S. Department of Energy. |
| Proceedings Inclusion? |
Planned: |