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Interaction of Rare Earth Chloride Salts to Alumina and Mullite in LiCl-KCl at 773 K
Horvath, David,Warmann, Stephen,King, James,Marsden, Kenneth,Hoover, Robert Korean Radioactive Waste Society 2020 방사성폐기물학회지 Vol.18 No.3
Two commonly used ceramics in molten salt research are alumina and mullite. The two ceramics were exposed to a combination of rare earth chlorides (YCl<sub>3</sub>, SmCl<sub>3</sub>, NdCl<sub>3</sub>, PrCl<sub>3</sub>, and CeCl<sub>3</sub>; each rare earth chloride of 1.8 weight percent) in LiCl-KCl at 773 K for approximately 13 days. Scanning electron microscopy with wave dispersion spectra was utilized to investigate a formation layer or deposition of rare earths onto the ceramic. Only the major constituents of the ceramics (Al, Si, and O<sub>2</sub>) were observed during the wave dispersion spectra. X-ray fluorescence was used as well to determine concentration changes in the molten salt as a function of ceramic exposure time. This study shows no evidence of ionic exchange or layer formation between the ceramics and molten chloride salt mixture. There are signs of surface tension effects of molten salt moving out of the tantalum crucible into secondary containment.
Experimental Observations for Anode Optimization of Oxide Reduction Equipment
David Horvath,James King,Robert Hoover,Steve Warmann,Ken Marsden,윤달성,Steven Herrmann 한국방사성폐기물학회 2022 방사성폐기물학회지 Vol.20 No.4
The electrochemical behavior was investigated during the electrolysis of nickel oxide in LiCl-Li2O salt mixture at 650℃ by changing several components. The focus of this work is to improve anode design and shroud design to increase current densities. The tested components were ceramic anode shroud porosity, porosity size, anode geometry, anode material, and metallic porous anode shroud. The goal of these experiments was to optimize and improve the reduction process. The highest contributors to higher current densities were anode shroud porosity and anode geometry.
Westphal, Brian,Tolman, David,Tolman, Kevin,Frank, Steven,Herrmann, Steve,Warmann, Stephen,Marsden, Kenneth,Patterson, Michael Korean Radioactive Waste Society 2020 방사성폐기물학회지 Vol.18 No.2
An options study was performed for the treatment of residual elemental sodium in driver plenums following the chopping operation during the pyroprocessing of used nuclear fuel. Given the pending availability of a multi-function furnace for distillation and consolidation operations in the Fuel Conditioning Facility, the furnace was considered for the processing of driver plenums. Although two options (oxidation and distillation) could be performed in the multi-function furnace, neither option has been developed sufficiently to date to warrant the use of the furnace for treatment operations. Thus, it was decided to defer the treatment of elemental sodium from driver plenums in the multi-function furnace until more developed technologies and/or furnaces become available. In the interim, storage of the plenums and characterization efforts are recommended.
Phase Behavior of the Ternary NaCl-PuCl3-Pu Molten Salt
Toni Karlsson,Cynthia Adkins,Ruchi Gakhar,James Newman,Steven Monk,Stephen Warmann 한국방사성폐기물학회 2023 방사성폐기물학회지 Vol.21 No.1
There is a gap in our understanding of the behavior of fused and molten fuel salts containing unavoidable contamination, such as those due to fabrication, handling, or storage. Therefore, this work used calorimetry to investigate the change in liquidus temperature of PuCl3, having an unknown purity and that had been in storage for several decades. Further research was performed by additions of NaCl, making several compositions within the binary system, and summarizing the resulting changes, if any, to the phase diagram. The melting temperature of the PuCl3 was determined to be 746.5°C, approximately 20°C lower than literature reported values, most likely due to an excess of Pu metal in the PuCl3 either due to the presence of metallic plutonium remaining from incomplete chlorination or due to the solubility of Pu in PuCl3. From the melting temperature, it was determined that the PuCl3 contained between 5.9 to 6.2mol% Pu metal. Analysis of the NaCl-PuCl3 samples showed that using the Pu rich PuCl3 resulted in significant changes to the NaCl-PuCl3 phase diagram. Most notably an unreported phase transition occurring at approximately 406°C and a new eutectic composition of 52.7mol% NaCl–38.7mol% PuCl3–2.5mol% Pu which melted at 449.3°C. Additionally, an increase in the liquidus temperatures was seen for NaCl rich compositions while lower liquidus temperatures were seen for PuCl3 rich compositions. It can therefore be concluded that changes will occur in the NaCl-PuCl3 binary system when using PuCl3 with excess Pu metal. However, melting temperature analysis can provide valuable insight into the composition of the PuCl3 and therefore the NaCl-PuCl3 system.