|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||In-situ Measurement of Tritium Release from Lithium Aluminate Under Neutron Irradiation
||Walter G. Luscher, David J. Senor, Gary N Hoggard
|On-Site Speaker (Planned)
||Walter G. Luscher
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 350 EFPD at 23 MWth. In-situ tritium measurements were obtained from capsules containing individual pellets. Each capsule was designed to provide both active temperature control and a sweep gas to carry any tritium released from the pellet to an ex-reactor measurement system. Results from these measurements were used to assess tritium release from γ-LiAlO2 as a function of burnup, burnup rate, and microstructure. Pellet microstructures were tailored to examine the effects of grain size (2-11 μm) and porosity (1-15%) on tritium release. In addition to these engineered microstructures, an alternate pellet design consisting of ~30μm γ-LiAlO2 granules dispersed in a zirconium matrix was also evaluated. An overview of the test train, capsule, and ex-reactor measurements systems will be provided in addition to the tritium release measurements.