About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
|
Symposium
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Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
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Presentation Title |
E-22: Corrosion Study of a Candidate Material for a Novel Telescopic Control Rod Design for High Temperature Gas Cooled Reactor Height Reduction |
Author(s) |
Gabriel Enzo Paramucchio, Ethan Fowler, Benjamin Lindley, Adrien Couet |
On-Site Speaker (Planned) |
Gabriel Enzo Paramucchio |
Abstract Scope |
High temperature gas reactors (HTGRs) require their core to be tall enough to effectively remove decay heat. Therefore, current designs involve traditional control rods seated above the core nearly doubling the excavation depth needed for their construction.
This research project aims to develop a telescopic control rod design to reduce the reactor’s height and thereby reduce its cost. However, this design poses materials degradation challenges, such as wear and corrosion.
A scaled-down prototype was manufactured out of 316LSS, and a specific corrosion experimental setup was built to allow us to expose the sample to a high temperature helium environment in a transparent tubular furnace. A driving mechanism also allows for the vertical extension and retraction of the telescopic rod. In-situ measurements of sliding velocity and deployment angle with image tracking and post corrosion characterization of the samples will be carried out to identify the feasibility of such a design. |
Proceedings Inclusion? |
Planned: |
Keywords |
High-Temperature Materials, Characterization, |