About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
C-16: Thermodynamic Assessment of the NaCl-ZrCl4, KCl-ZrCl4, and MgCl2-ZrCl4 Systems for Molten Chloride Reactors |
| Author(s) |
Jack A. Wilson, Juliano Schorne-Pinto, Mina Aziziha, Ronald E. Booth, Hunter B. Tisdale, Hans-Conrad zur Loye, Theodore M. Besmann |
| On-Site Speaker (Planned) |
Jack A. Wilson |
| Abstract Scope |
Zirconium is a significant fission product with long-lived isotopes which interacts in molten chloride reactors with solvent fuel salt components such as NaCl, KCl, and MgCl2. In this study, the NaCl-ZrCl4, KCl-ZrCl4, and MgCl2-ZrCl4 systems are thermodynamically assessed, including optimization of the thermodynamic values for the endmember, ZrCl4, and interaction parameters for the pseudo-binary systems have been determined. Models are validated with differential scanning calorimetric measurements where possible. The resulting models and other descriptions are available in the open-source compendium Molten Salt Thermal Properties Database - Thermochemical (MSTDB-TC). |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Phase Transformations, Modeling and Simulation |