| About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
2024 Undergraduate Student Poster Contest
|
| Presentation Title |
SPU-30: Investigating Thermophysical Properties of Uranium Nitride Nuclear Fuel |
| Author(s) |
Sarah Cole, Ryan Finkelstein, Allyssa Bateman, Elizabeth Sooby, Brian Jaques |
| On-Site Speaker (Planned) |
Sarah Cole |
| Abstract Scope |
Uranium nitride (UN) is an advanced nuclear fuel candidate distinguished by its high uranium density of 13.5 g-U/cm3 and a thermal conductivity of 13.6 W/m*K (300°C, 95% TD) which improves with temperature. In this study, UN powder was synthesized from UO2 and carbon precursors using the carbothermic reduction prior to nitriding method, which leverages the existing UO2 supply chain and is a commercially scalable synthesis route for metal nitrides. Disc shaped samples of 1 cm diameter and nominally 2 mm height were pressed at 350 MPa and densified to >90% theoretical density using pressureless sintering. Oxygen impurities were analyzed using combustion analysis and thermal diffusivity experiments were performed using Laser Flash Analysis. Results show that the fabricated UN is phase pure with low oxygen impurities of less than 750 ppm. The influence of manufacturing methods on light element impurities and thermophysical properties will inform performance criteria towards fuel qualification. |