About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Mechanical Response of Materials Investigated through Novel In-situ Experiments and Modeling
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Presentation Title |
Post-Quench Ductility of FeCrAl Alloys Subjected to High Heating Rates |
Author(s) |
Victoria Davis, Caleb King, Jessika Rojas, Carlos Castano, Reza Mohammadi, Braden Goddard, Tristan Norrgard, Rajnikant Umretiya, Colson Miller |
On-Site Speaker (Planned) |
Victoria Davis |
Abstract Scope |
Since the reactor meltdown at Fukushima Daiichi in 2011, there has been a large push toward developing and implementing Accident Tolerant fuels (ATFs). Iron-chromium-aluminum (FeCrAl) alloys are promising cladding candidates based on superior mechanical and oxidation resistance compared to the current nuclear standard, Zircaloy-4 (Zr-4). This work investigated the mechanical properties of two FeCrAl alloys as potential ATF claddings under critical oxidative environments and quenching. A high-temperature, high ramp-rate apparatus has been developed to simulate LOCA reactor conditions, allowing quenching steps. Following the high-temperature testing, the mechanical properties of the FeCrAl specimens were assessed using ring compression and a mechanical system developed to simulate cladding hoop stresses that occur during the dry storage process. In analyzing the FeCrAl tested specimens, the strength, ductility, and hardness were assessed to determine how their properties change under the implemented testing environments. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Mechanical Properties, Nuclear Materials |