About this Abstract |
| Meeting |
MS&T26: Materials Science & Technology
|
| Symposium
|
TMS Frontiers of Materials Award Symposium: Surface Engineering for Nuclear Energy: An Additive Manufacturing Perspective
|
| Presentation Title |
Advancing the Next-Generation Nuclear Systems Through Graphite Tribology |
| Author(s) |
Tomas Grejtak, Nidia C. Gallego, Jun Qu |
| On-Site Speaker (Planned) |
Tomas Grejtak |
| Abstract Scope |
Fluoride salt-cooled and high-temperature gas-cooled pebble-bed reactors contain thousands of circulating graphitic fuel pebbles that repeatedly slide and roll against neighbouring pebbles and reactor structures during operation. These mechanical interactions induce structural abrasion, the generation of fission-product-contaminated graphite dust, and potential alterations to fuel circulation. Consequently, a comprehensive tribological characterization of nuclear graphite is critical for ensuring long-term reactor safety and reliability. This study evaluates the friction and wear behaviour of nuclear-grade graphite in both molten FLiNaK salt and dry inert argon environments to investigate the effects of temperature, contact load, and sliding speed. The wear mechanisms are characterized via high-resolution electron microscopy and Raman spectroscopy. These results provide essential data for assessing the durability of fuel pebbles, directly supporting the safe and dependable operation of next-generation reactor systems. |