| About this Abstract |
| Meeting |
MS&T22: Materials Science & Technology
|
| Symposium
|
Ceramics for a New Generation of Nuclear Energy Systems and Applications
|
| Presentation Title |
Corrosion of SiC in Molten Salt and Liquid Lead |
| Author(s) |
Huali Wu, Jinsuo Zhang |
| On-Site Speaker (Planned) |
Huali Wu |
| Abstract Scope |
Ceramic composites based on silicon carbide fibers with a silicon carbide matrix (SiC-SiC) have been studied for use in advanced nuclear reactors such as molten salt reactors and lead-cooled fast reactors and show very promising results in both corrosion and radiation tolerance. The present study tested SiC corrosion by liquid lead and U-bearing molten fluoride salt. All the tests were conducted at 700 oC in the static liquid for 120 hours. The post-test samples were characterized by SEM and XRD. The characterization was focus on the Si depletion layer, the oxidation layer, and the liquid infiltration. Different SiC samples with different fabrication methods were tested, and results showed that fabrication method may influence the corrosion resistance of SiC to both molten salt and liquid lead. |