| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
In-situ Characterization of FeCrAl Claddings Under Simulated LOCA Conditions |
| Author(s) |
Samuel Bell, Mackenzie Ridley, David Hoezler, Nathan Capps, Caleb Massey |
| On-Site Speaker (Planned) |
Samuel Bell |
| Abstract Scope |
Emergent nuclear cladding candidates, such as ferritic FeCrAl alloys, have exhibited superior accident tolerance with increased mechanical strength and steam oxidation resistance compared to conventional Zr alloys. Understanding cladding behavior and the implications of these improvements during design-basis accidents, such as loss-of-coolant accidents (LOCAs), is pivotal for development of predictive performance models. Recent efforts have integrated digital image correlation techniques to measure strain in-situ during simulated LOCA experiments. Such a framework synchronizes temperature, stress, and strain, allowing for deeper investigations into cladding behavior and ultimately more rapid model development. FeCrAl claddings were internally pressurized and subjected to a simulated LOCA heating transient until rupture. Thermal creep and plasticity information were extracted to inform deformation mechanisms. Stress exponents will be compared with creep data extracted from axially-loaded tubes subjected to axial creep tests. This work was supported by the United States Department of Energy, Office of Nuclear Energy, Advanced Fuels Campaign. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Characterization |