|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Powder Materials Processing and Fundamental Understanding
||Powder Metallurgy Fabrication of ZrHx Moderator and U-ZrHx Moderated Nuclear Fuel
||Caitlin Taylor, Erik Luther, Adrian R Wagner, Thomas Nizolek, Aditya Shivprasad, Tarik Saleh
|On-Site Speaker (Planned)
Metal hydrides have long been considered for neutron moderator applications in nuclear energy systems due to their high temperature stability compared to water, for example. Zirconium hydride (ZrHx) fabrication typically involves exposing a machined Zr component to hydrogen at elevated temperature. The volume expansion between metallic Zr and the hydride phase is approximately 16%, often resulting in cracking or large residual stress gradients. Some reactor concepts utilize uranium-zirconium hydride (U-ZrHx) moderated nuclear fuel. Fabrication of U-ZrHx traditionally follows a direct-hydriding route similar to that of ZrHx, but starting with U-Zr alloy. A powder metallurgy method for yttrium hydride (YHx) fabrication was recently developed at LANL by Shivprasad et al. In this work, we build on previous work to develop a method for fabricating ZrHx and U-ZrHx by powder metallurgy. The fabrication route and resulting microstructures will be discussed and compared to direct-hydrided material. LA-UR-21-26357.
||Powder Materials, Process Technology, Nuclear Materials