| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
Processing and Irradiation Damage in Novel Tritium Breeding Ceramics with High Lithium Content |
| Author(s) |
David Armstrong |
| On-Site Speaker (Planned) |
David Armstrong |
| Abstract Scope |
In this work we will demonstrate the synthesis of high phase purity octolithium compounds, of general formula Li8XO6 where X can be Pb, Zr, Sn, Ge. The complex multi stage reaction is characterised using in situ XRD. This shows significant differences in the four manufacture routes and allows for optimisation of the processing conditions. The materials are then characterised using SEM, EDX and nanoindentation. The mechanical properties measured show excellent agreement with DFT predictions of elastic modulus. Alpha particle irradiation was carried out to simulate neutron damage and transmutation. This has been characterised using Ramen spectroscopy and nanoindentation, showing significant microstructure degradation and embrittlement. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Environmental Effects, Nuclear Materials |