| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Formation of UN in U-Mo Systems by Mechanical Alloying |
| Author(s) |
James M. Zillinger, Nathan Jerred, Adrian Wagner, Samrat Choudhury, Indrajit Charit |
| On-Site Speaker (Planned) |
James M. Zillinger |
| Abstract Scope |
U-Mo alloys show promise as a nuclear fuel system due to their high thermal conductivity and high fuel loading capability. However, U-Mo systems suffer from irradiation induced swelling ultimately affecting the cladding via mechanical and chemical interaction. To address these shortcomings, this work investigated the formation of UN particles within a U-10Mo matrix to improve its irradiation performance. To promote the formation of UN, U-10Mo powders were milled under a high purity N2 atmosphere. Subsequent analysis has shown nitrogen successfully diffused into the alloy. Milling times, intensities (rpm), and media sizes were varied to observe their effects on resulting material characteristics. Mechanically alloyed powders were thermally treated to induce the formation of a UN phase. Powder and feedstock alloy samples were analyzed via light-elemental analysis, dissolution chemistry, SEM, XRD, and TEM to provide a clear understanding of how every step of the material processing affected fuel behavior and microstructure. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Powder Materials, Other |