Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation

Sridharan, Kumar; Allen, Todd R.; Anderson, Mark; Simpson, Mike

doi:10.2172/1058922

Cited by 38 publications

(51 citation statements)

References 30 publications

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“…LiCl-KCl melts were prepared by mixing LiCl (Alfa Aesar 99% pure) and KCl (Alfa Aesar 99% pure) at 46 wt.% and 54 wt.%, respectively. 26 Precursor salts utilized to prepare the final eutectic were first baked under vacuum at 200 ˚C in order to minimize moisture-induced impurities. Anhydrous SmCl 3 (Alfa Aesar, 99.9% pure) was dissolved directly into the molten LiCl-KCl eutectic at 500 ˚C and agitated for eight hours.…”

Section: Samarium Oxychloride Synthesismentioning

confidence: 99%

An Investigation of Synthesized Samarium Oxychloride in Molten LiCl-KCl

Singh¹,

Bruneau²,

Karmiol³

et al. 2019

Preprint

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Section: Samarium Oxychloride Synthesismentioning

confidence: 99%

An Investigation of Synthesized Samarium Oxychloride in Molten LiCl-KCl

Singh¹,

Bruneau²,

Karmiol³

et al. 2019

Preprint

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“…So the imprecision on the values of Gibbs free energy of fusion will result in a small error in our results. Also, the comparisons of activity coefficients in other literatures [11,58] are based on the same order of magnitude. It should be thought the comparisons are acceptable if the calculated activity coefficients of RECl 3 in molten salt and literature values are in the same order of magnitude.…”

Section: Lanthanummentioning

confidence: 99%

Investigation of concentration-dependence of thermodynamic properties of lanthanum, yttrium, scandium and terbium in eutectic LiCl-KCl molten salt

Zhou

Zhang

2016

Journal of Nuclear Materials

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Thermodynamic properties of rare earth metals in LiCl-KCl molten salt electrolyte are crucial to the development of electrochemical separation for the treatment of used nuclear fuels. In the present study, activity coefficient, apparent potential, and diffusion coefficient of lanthanum, yttrium, scandium, and terbium in the molten salt (58 at% LiCl and 42 at% KCl) were calculated by the method of molecular dynamics simulation up to a concentration around 3 at% at temperatures of 723 K and 773 K. It was found that the activity coefficient and the apparent potential increase with the species concentration while diffusion coefficient shows a trend of increase followed by decrease. The calculated results were validated by available measurement data of dilution cases. This research extends the range of data to a wide component and would provide further insight to the pyroprocessing design and safeguards.

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“…1,2 LiCl-KCl eutectic salt is the electrochemical media for the reprocessing of used nuclear fuel (UNF) through pyrochemical methods. [3][4][5][6][7][8][9] An understanding of chloride salt chemistry may offer insight into the corrosion behavior of proposed structural materials, and process optimization as it pertains to reprocessing and nuclear material accountancy (NMA) in salt systems containing special nuclear material (SNM). Furthermore, in situ techniques for the analysis and monitoring of salt content offer a path toward commercialization for many of these advanced reactor and reprocessing concepts.…”

Section: Introductionmentioning

confidence: 99%

In situ Raman spectroscopy of samarium ions in molten LiCl-KCl eutectic

Singh¹,

Bruneau²,

Chidambaram³

2019

Preprint

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A fiber-based Raman spectroscopy system was commissioned in an inert atmosphere for in situ analysis of high temperature molten salts. Speciation of samarium chloride was studied in the LiCl-KCl eutectic system at 500 °C. Raman spectra indicated trivalent samarium forms an octahedral SmCl63- complex with two detectable vibration modes. Chemical reduction experiments were conducted to investigate the coordination of divalent samarium in the same eutectic salt. The resulting spectra are reported and discussed in terms of complex formation and behavior of divalent samarium ions. Trivalent samarium was electrochemically reduced in situ and Raman spectra obtained were compared with those resulting from chemical reduction experiments. The spectra suggest divalent samarium ions form in LiCl-KCl only temporarily and spontaneously disproportionate into a mixture of trivalent samarium ions and metallic samarium.

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Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation

Cited by 38 publications

References 30 publications

An Investigation of Synthesized Samarium Oxychloride in Molten LiCl-KCl

An Investigation of Synthesized Samarium Oxychloride in Molten LiCl-KCl

Investigation of concentration-dependence of thermodynamic properties of lanthanum, yttrium, scandium and terbium in eutectic LiCl-KCl molten salt

In situ Raman spectroscopy of samarium ions in molten LiCl-KCl eutectic

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