| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
|
| Presentation Title |
Impact of Pre-existing Damage on He Irradiated Sintered 3C-SiC |
| Author(s) |
Nabil Daghbouj, Bingsheng Li, Miroslav Karlik, Mauro Callisti, Tomas Polcar, Huseyin Sener |
| On-Site Speaker (Planned) |
Nabil Daghbouj |
| Abstract Scope |
Helium platelets are created in He irradiated sintered 3C-SiC at high temperature with high fluence. These platelets are the precursor of blisters and exfoliation, and in order to prevent their formation, pre-existing damage is induced in sintered SiC. The irradiation of He under the same condition (high temperature and high fluence) induce only nanobubbles. These samples are studied using the combination of energy recoil detection analysis (ERDA), and transmission electron microscopy (TEM) characterization. Our finding demonstrated that SiC contains damage such as vacancies that are dispersed in a wide region and play as a trapping center for He which can lead to decreased He diffusivity (prevent Ostwald repining) and avoid coalescence phenomena. A detailed analysis using ab initio simulation (DFT) revealed that it is energetically very expensive for He atoms to leave a void making Ostwald and coalescence phenomena unlikely. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Modeling and Simulation |