| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
|
| Presentation Title |
Development and Construction of a Liquid Lead-Lithium Loop at UNM |
| Author(s) |
Xavier Angus, Sergey Smolentsev, Bruce Pint, Claude De lamater-Brotherton, Marie Romedenne, G. Ivan Maldonado, Nicholas Brown, Quang Son, Michael Trombetta, Daniel Levario, Osman Anderoglu |
| On-Site Speaker (Planned) |
Xavier Angus |
| Abstract Scope |
Studying the challenges associated with lead-lithium eutectic, especially structural materials compatibility of liquid lead-lithium is necessary to ensure the long-term viability of a lead-lithium-cooled blanket for use in a fusion reactor. This project involves the design and construction of a forced convection lead-lithium loop out of SS316 to test corrosion rates at high flow rates (up to 1 m/s) and temperatures (up to 500° C) in the presence of an external magnetic field. The key components of this loop include removable tubing sections for inserting test material, a high-powered electromagnet (~2T), and a capacity of three gallons of lead-lithium. The electromagnet enables pressure drop studies and corrosion tests at high magnetic fields, simulating the environment in a blanket. The loop also incorporates various instrumentation such as a Venturi flow meter and differential pressure sensors for MHD and flow accelerated corrosion studies. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, |