|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Oxidation Behavior of TRISO Fuel Materials
||Haiming Wen, Adam Bratten, Visharad Jalan
|On-Site Speaker (Planned)
While high-temperature gas reactors use pure helium as a reactor coolant, in some accident scenarios significant amounts of moisture or air can be introduced into the helium coolant and reactor core. It is important to understand the oxidation and degradation processes exhibited by both TRISO particles (particularly the SiC layer) and matrix graphite under these conditions. In this study, matrix graphite and surrogate TRISO particles (with ZrO2 kernel) were subjected to oxidation by air and/or moisture under conditions relevant to the air/moisture ingress accidents, using thermogravimetric analysis (TGA) – differential scanning calorimetry (DSC) or custom-built tube furnace setup. The kinetic parameters of oxidation were measured through the oxidation studies at different temperatures with different partial pressure of oxygen or water vapor. The microstructures of the materials before and after oxidation were carefully characterized. The oxidation mechanisms were ascertained in relation to the oxidation conditions and microstructures of the materials.
||Nuclear Materials, Characterization, Ceramics