|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||O-1: Uranium Silicide Processing for Advanced Reactors
||Zach Huber, Elise Conte
|On-Site Speaker (Planned)
This poster will show advances in key elements of uranium silicide (U3Si2) processing science. Pacific Northwest National Laboratory under the United States High Performance Research Reactor Project has been investigating multiple attributes of high quality U3Si2 dispersion fuel. Investigations include oxidation, mechanical behavior, particle size distribution effects on homogeneity, thermal conductivity as well as many other aspects regarding the processing and fabrication of dispersion fuels. This poster will highlight some of the areas of research interest with the U3Si2-Al dispersion fuel.
||Composites, Nuclear Materials, Powder Materials