|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||TMIST-3A Post-irradiation Examination
||Mark S. Lanza, Walter G. Luscher, David J. Senor, Gary N. Hoggard
|On-Site Speaker (Planned)
||Mark S. Lanza
Gamma-lithium aluminate (γ-LiAlO2) pellets with engineered microstructures were irradiated in the Advanced Test Reactor between September 2016 and January 2019 for a total of 350EFPD at 23MWth. Tritium speciation was studied by placing the pellets in individual capsules and surrounding them with components that preferentially react with either T2 or T2O. Post irradiation examination (PIE) is expected to reveal the fractionation between T2 and T2O released during irradiation. In addition to engineered microstructures with varying porosity and grain size, an alternate pellet design consisting of ~30μm γ-LiAlO2 granules dispersed with volume fractions (0.1-0.4) in a zirconium matrix was irradiated. Comparison between standard LiAlO2 and LiAlO2/Zr designs is expected to reveal the effects of encapsulating LiAlO2 granules in a Zr matrix on tritium release and speciation. This presentation will provide an overview of the experiment and anticipated PIE campaign as well as recently obtained measurement data from ongoing PIE activities.