|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Emulation of Microstructures and Tritium Behavior in Lithium Aluminate by Ion Irradiation
||Weilin Jiang, Libor Kovarik, Zihua Zhu, Walter G. Luscher, Andrew M. Casella, David J. Senor
|On-Site Speaker (Planned)
Gamma-phase lithium aluminate (γ-LiAlO₂) has been investigated as a candidate material for fusion reactor blankets and has been utilized for tritium production. The material has an outstanding thermomechanical stability and low-swelling behavior under neutron irradiation. Defects are generated in the material during irradiation of fast neutrons and the energetic helium and tritium particles from nuclear reaction ⁶Li (n, He) T. It is important to investigate the microstructural evolution and its impact on T diffusion and release in order to assess and predict the material performance during neutron irradiation. Over the past years, we have performed emulation of microstructural evolution as well as T and Li transports in γ-LiAlO₂ pellets using sequential irradiation of He⁺ and D⁺ (a surrogate for T⁺) ions at elevated temperatures. This presentation will provide an overview of the results, including a comparison of microstructures and species transport behavior in ion and neutron irradiated γ-LiAlO₂ pellets.
||Ceramics, Nuclear Materials, Phase Transformations