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 |
D-38: Oxidation and Post-quench Ductility of Chromium Coated Zircaloy-4 |
Author(s) |
Victoria Davis, Caleb King, Colson Miller, Tristan Norrgard, Braden Goddard, Carlos Castano, Reza Mohammadi, Rajnikant Umretiya, Jessika Rojas |
On-Site Speaker (Planned) |
Victoria Davis |
Abstract Scope |
This work investigates the mechanical properties of chromium-coated Zircaloy-4 (Zr-4) as a potential accident tolerant fuel (ATF) cladding following high temperature oxidation environments and quenching. Since the 2011 Fukushima Daiichi reactor meltdown highlighted a key drawback of Zr-4, there has been a large push towards the development and implementation of ATFs. A promising near-term solution is the addition of a chromium coating on the exterior of the Zr-4 to decrease oxidation kinetics in extreme reactor conditions. To further examine Cr-coated Zr-4, a high temperature, high ramp-rate apparatus has been developed to simulate LOCA reactor conditions. Following the rapid temperature excursion testing at multiple temperatures and quenching, the mechanical properties of the tested specimens were evaluated using ring compression and a device developed to simulate cladding hoop stresses that occur during the dry storage process. Each specimen was examined in terms of hardness, strength, ductility, and their correlation with their microstructure. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Mechanical Properties, Nuclear Materials |