About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials and Chemistry for Molten Salt Systems
|
Presentation Title |
Structural and Thermochemical Investigations of Intermediate Compounds in the CsCl-UCl3 and NaCl-CsCl-UCl3 systems |
Author(s) |
Aiswarya Padinhare Manissery, Juliano Schorne-Pinto, Hunter B Tisdale, Hans-Conrad zur Loye, Theodore M Besmann |
On-Site Speaker (Planned) |
Aiswarya Padinhare Manissery |
Abstract Scope |
The TerraPower molten chloride reactor experiment uses NaCl as the carrier salt and UCl3 as the primary fissile material. One of the major fission products is cesium, which can cause extensive environmental contamination during a major release, owing to its high volatility and radiotoxicity; therefore, its behavior is of considerable interest. Cesium can generate a series of intermediate compounds in the CsCl-UCl3 (i.e., Cs3UCl6, Cs2UCl5, CsUCl4 and CsU2Cl7) and the NaCl-CsCl-UCl3 (i.e., Cs2NaUCl6) systems, resulting in complex phase equilibria. Despite their significance, limited structural and thermodynamic data are available for these compounds. Present study involves a comprehensive experimental investigation to synthesize these compounds, and evaluate their phase purity. Enthalpy of fusion and heat capacity of these compounds were subsequently determined by differential scanning calorimetry to construct the respective binary phase diagrams. Resultant thermochemical properties will be available in future versions of the Molten Salt Thermal Properties Database – Thermochemical (MSTDB-TC). |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Other |