About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Materials and Chemistry for Molten Salt Systems
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Presentation Title |
Evaluation and Thermodynamic Modeling of Molten Salt Reactor Fuel Compositions Applications: Study of Case of NaCl-UCl3-PuCl3 and LiF-BeF2-ZrF4-UF4 Systems |
Author(s) |
Juliano Schorne Pinto, Mina Aziziha, Jacob Yingling, Johnathon Ard, Jorge Paz Soldan Palma, Amir M. Mofrad, Theodore M. Besmann |
On-Site Speaker (Planned) |
Juliano Schorne Pinto |
Abstract Scope |
The new generation of nuclear reactors (Gen IV) has received growing attention over the last two decades targeting improved safety, sustainability, efficiency, and cost. Among the proposed designs, molten chloride reactors and molten fluoride reactors are promising options, although they face the challenge of developing sufficient basic information to reliably build, operate, and regulate them. That understanding includes being able to represent the complex thermostructural evolution of the melt as a function of temperature and composition, which produces no neglectable influence on the bulk thermochemical properties. The development of thermodynamic models for NaCl-UCl3-PuCl3 and LiF-BeF2-ZrF4-UF4 systems within the Molten Salts Thermodynamic Database – Thermochemical (MSTDB-TC) will be used to demonstrate how they can be globally capture these thermostructural changes, thus realistic representing phase equilibria, specific heat, and vapor pressures. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Computational Materials Science & Engineering, Nanotechnology |