|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Radiolytic Damage and Hydrogen Generation at Carbide – Water Interfaces
||Simon M. Pimblott, Jay A. LaVerne
|On-Site Speaker (Planned)
||Simon M. Pimblott
Carbides have great potential for application in the nuclear industry; however, various properties require detailed understanding for the materials to be properly utilized in situations where they will be exposed to extreme temperatures and mixed radiation fields. The behavior of SiC and ZrC as well as water slurries have been systematically studied using gamma and alpha radiation. Damage to the carbides was determined using analytical techniques including TGA, ICP-OES and SEM-EDS. Gamma irradiation of ZrC in air results in a change in Zr:C ratio with SEM examination showing oxidation of the surface. SiC is relatively stable under gamma irradiation except for some conversion of β to the α phase: α-ray radiolysis leads to the formation of SiO<sub>2</sub>. Aqueous slurry irradiations yield a large increase in the radiolytic yield of hydrogen compared to water, an effect that could have significant deleterious consequences if the material is deployed in nuclear energy environs.