| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications III
|
| Presentation Title |
Analyzing Advanced Composite Shield Materials for Fusion and Space Reactor Applications |
| Author(s) |
Mediha Merve Karatas, Steven John Zinkle |
| On-Site Speaker (Planned) |
Mediha Merve Karatas |
| Abstract Scope |
Ceramics are promising candidate matrix materials for high performance composite radiation shields, due to their low H permeation, high thermal conductivity, and high thermodynamic stability. LiF doping of MgO and ZrN powder was investigated to potentially reduce the sintering temperature and thereby minimize dissociation of HfH2 particles in the composite during spark plasma sintering (SPS). LiF addition did not affect SPS sintering for ZrN whereas a strong reduction in sintering temperature occurred for MgO. The scientific mechanisms responsible for the difference in sintering behavior of these two ceramics were investigated by modeling and experimental studies including Differential scanning calorimeter (DSC) and Synchrotron-based XRD. Differences in LiF solubility, which directly affects Schottky vacancy production, is considered to be an important factor. Hydrogen isotope permeation measurements on sintered MgO and ZrN as a function of temperature will be compared with model predictions to quantify hydrogen permeation to/from the composite radiation shield. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Characterization, Nuclear Materials |