TD
T. Dumaire
6 records found
1
The present study describes the thermodynamic assessment of three pseudo-binary systems relevant to CsI solubility in molten iodide salts: KI-CsI, NaI-CsI, and NaF-CsI. The motivation for this study was to corroborate a single previously reported data set of the NaI-CsI system, r
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Lithium-based fluoride salts are one of the leading options as fuel matrix in Molten Salt Reactors. The understanding of their thermodynamic behavior, e.g. chemical stability, activity, as well as heat transfer properties, in the reactor’s environment is crucial for the safety as
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This work examines the thermochemistry of the chromium difluoride CrF2 corrosion product in the molten [Formula presented] fuel salt system. Through a combination of experimental investigations and thermodynamic modeling assessment, the study elucidates the thermodynam
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TheMolten Salt Reactor (MSR) is probably the most promising design of the 4th generation for the future of nuclear energy. The liquid nature of the fuel and the implementation of innovative safety measures could, in time, open up access to energy from atomic fission to the whole
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A promising fuel for fast neutron spectrum Molten Salt Reactor
NaCl-ThCl4-PuCl3
Chloride salts are considered a good alternative to fluoride salts as fuel carrier in the Molten Salt Fast Reactor concepts. The NaCl–ThCl4–PuCl3 fuel salt solution seems very promising, with low melting temperature eutectic compositions, and the potential to be used in a breeder
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Understanding the corrosion mechanisms and the effect of corrosion products on the basic properties of the salt (e.g., melting point, heat capacity) is fundamental for the safety assessment and durability of molten salt reactor technology. This work focused on the thermodynamic a
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