Abstract
The extensively evaluated and consistent thermodynamic database, the Molten Salt Thermal Properties Database—Thermochemical (MSTDB-TC), was used along with additional thermodynamic values from other sources as examples of ways to examine molten salt reactor (MSR) fuel behavior. Relative stability with respect to halide potential and temperature for likely fuel and fission product components were mapped in Ellingham diagrams for the chloride and fluoride systems. The Ellingham diagrams provide a rich, visual means for identifying halide-forming components in proposed fuel/solvent salt systems. Thermochemical models and values from MSTDB-TC and ancillary sources were used in global equilibrium calculations to provide compositions for a close analysis of the behavior of a possible Molten Chloride Salt Fast Reactor and a Molten Salt Reactor Experiment-type system at high burnup (100 GWd/t). The results illustrated the oxidative nature of burnup in MSRs and provided information about redox behavior and possible control.
Original language | English |
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Article number | 495 |
Journal | Materials |
Volume | 17 |
Issue number | 2 |
DOIs | |
State | Published - Jan 2024 |
Funding
This research was supported by the U.S. DOE Office of Nuclear Energy, the Nuclear Energy Advanced Modeling and Simulation Program; the Molten Salt Reactor Program; and the Nuclear Energy Universities Program, project DE-NE0008985.
Keywords
- CALPHAD
- fission products
- molten salts
- redox