About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
2026 Technical Division Student Poster Contest
|
| Presentation Title |
SPU-40: Development and Utilization of a Linear Gradient Density Column for Characterization of Advanced Nuclear Fuel |
| Author(s) |
Allison Niblett, Patrick Morrison, James Buckley, Kaylee Rich, Anil Prasad |
| On-Site Speaker (Planned) |
Allison Niblett |
| Abstract Scope |
TRi-structural ISOtropic (TRISO) fuel is the primary fuel choice for High Temperature Gas Reactors and a few microreactor concepts. Each TRISO particle acts as its own containment for fission products, with the silicon carbide (SiC) layer serving as the primary barrier. A representative batch of TRISO particles are characterized prior to use to ensure their properties meet the required fuel specifications. A linear density gradient column is the standard method for destructively determining the density of various layers within the TRISO particle. To establish a controlled density gradient within a column, two miscible liquids are utilized whose densities bound the target range. Canadian Nuclear Laboratories has developed an in-house setup to measure densities of TRISO layers. This work provides insights into the advantages and challenges of this method and benchmark measurements to facilitate the development of novel and alternative characterization techniques. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
Characterization, Nuclear Materials, Ceramics |