Anodic dissolution of U, Zr and U–Zr alloy and convolution voltammetry of Zr4+|Zr2+ couple in molten LiCl–KCl eutectic

Ghosh, Suddhasattwa; Vandarkuzhali, S. Anbu Anjugam; Gogoi, Nibedita; Venkatesh, P.; Seenivasan, G.; Reddy, B. Prabhakara; Nagarajan, K.

doi:10.1016/j.electacta.2011.06.027

Cited by 41 publications

(38 citation statements)

References 25 publications

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“…And the electrochemical behavior of Zr at a liquid Cd electrode for recovering Zr on Cd electrode has also been investigated. The chemical equilibration of U-Pu-Zr fuel with stoichiometric amounts of CdCl 2 in LiCl-KCl molten salt, which leads to the formation of UCl 3 and PuCl 3 , has also been reported by Kuznetsov et al [16] and Ghosh et al [17]. However, the chlorinating and oxidizing agent, CdCl 2 is toxic and expensive, and the final product Cd will be an impurity and cause heavy metal pollution.…”

Section: Introductionmentioning

confidence: 86%

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Cai

Liu

et al. 2015

Electrochimica Acta

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Section: Introductionmentioning

confidence: 86%

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Cai

Liu

et al. 2015

Electrochimica Acta

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“…The exchange current densities of uranium in the molten salt have been reported with few different methods. [11][12][13] As shown in Figure 14, the reported i 0 for U 3+ /U reaction is scattered in the order from 10 −2 to 10 −1 ; thus, it is difficult to compare each data or observe its trend. The main reason of the deviation could be that the authors performed the different methods to measure i 0 at different temperatures and concentrations, and also be the challenges that have been previously mentioned.…”

Section: Electrochemical Impedance Spectroscopy (Eis)-mentioning

confidence: 99%

“…Later, Ghosh and co-workers reported that the exchange current density of uranium is 8 ± 2 mA cm −2 , by measurements of Tafel plot. 12 Rose et al in 2015 13 measured the exchange current density of uranium from Tafel plot, ranging from 69.5 ± 9 to 220 ± 32 mA cm −2 . From these literature z E-mail: yoond2@vcu.edu results, a meaningful comparison of the reported data is not possible owing to the dispersed values of the exchange current density of uranium.…”

mentioning

confidence: 99%

“…Only few studies on the exchange current densities of uranium in LiCl-KCl have been published. [11][12][13] Choi et al in 2009 11 performed a linear polarization method in LiCl-KCl at 773 K and reported the exchange current density of uranium ranging from 0.3 to 0.5 A cm −2 . Later, Ghosh and co-workers reported that the exchange current density of uranium is 8 ± 2 mA cm −2 , by measurements of Tafel plot.…”

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confidence: 99%

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Electrochemical Properties and Analyses of CeCl₃in LiCl-KCl Eutectic Salt

Yoon

Phongikaroon

2015

J. Electrochem. Soc.

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Thermodynamic and electrochemical properties of cerium in LiCl-KCl eutectic salt have been measured and studied at different concentrations (0.5 -4 wt%) and temperatures (698 K -798 K) via both cyclic voltammetry (CV) and electrochemical impedance spectroscopy (EIS) techniques as a part of developing a fundamental understanding and methodology in materials detection and accountability for pyroprocessing technology. CV experiments were performed to determine the diffusion coefficient and apparent standard potential of CeCl 3 on the tungsten working electrode. The diffusion coefficient was calculated by using Delahay equation, and raging from 0.48 × 10 −5 to 1.01 × 10 −5 cm 2 s −1 . Results reveal that the calculated diffusion coefficient of CeCl 3 in the salt follows the Arrhenius temperature relationship and it is weakly affected by the changes in concentration of CeCl 3 . The apparent standard potentials were calculated from peak potentials showing linear relationship with temperature. Exchange current density values of Ce 3+ /Ce couple in the salt were obtained from EIS experiments, ranging from 0. Pyroprocessing technology has been proposed as another promising method for the recovery and recycle of uranium and actinide elements from the used nuclear fuel. An essential step in this technology is the electrorefining process in which uranium is selectively recovered by using solid cathodes in chloride-based molten salt at high temperature.1 Then, co-recovery of uranium and transuranic elements can be accomplished by replacing the solid cathodes with a liquid cadmium cathode because the reduction potentials of the elements become close when the liquid cadmium is used as a cathode electrode.2,3 Since uranium is the major element in most nuclear fuel cycle paths as well as pyroprocessing technology, the assessment of accurate thermochemical data for the element in the molten salt is extremely important. 4Many studies on the thermochemical properties of uranium have been done in LiCl-KCl molten eutectic salt in different temperature ranges. Masset et al. 5,6 investigated diffusion coefficients of actinides and lanthanides in LiCl-KCl via cyclic voltammetry (CV) and chronopotentiometry (CP). Kuznetsov et al. 7,8 studied the electrochemical behaviors of actinides and rare-earth metals in LiCl-KCl salt. They performed CP and chronoamperometry (CA), and linear sweep voltammetry to determine the diffusion coefficients. Hoover et al. in 2014 9 extended the uranium concentration in LiCl-KCl molten salt up to 10 wt% and observed the electrochemical and thermodynamic behaviors of uranium using CV, CP, and anodic stripping voltammetry. These data are valuable to a development of kinetic models, which can be useful for understanding the main features of actinide deposition at the electrode surface, and also for prediction of material distribution in an electrorefiner of a safeguarding aspect. Zhang 10 developed a kinetic model for electrorefining system showing that the model is capable of predicting the kinetic features and...

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“…The R&D (Kutty et al, 2009;Reddy et al, 2010;Nagarajan, 2010;Nagarajan et al, 2011;Sri Maha Vishnu et al, 2012;Ghosh et al, 2009Ghosh et al, , 2011Vandarkuzhali et al, 2012) at IGCAR (Indira Gandhi Centre for Atomic Research) in the area of molten salts is comprehensive and includes studies with respect to electrowinning of actinide oxides, separation processes linked to fluoride-based systems relevant to MSRs, and recycling fuel by dissolution in tin as well as electrorefining of metal fuel. In the area of electrorefining, the work comprises research in the areas of the following: Reduction studies include calciothermic reduction of metal fluorides and the DER of oxide.…”

Section: Indiamentioning

confidence: 99%

International developments in electrorefining technologies for pyrochemical processing of spent nuclear fuels

Lewin

Harrison

2015

Reprocessing and Recycling of Spent Nuclear Fuel

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Anodic dissolution of U, Zr and U–Zr alloy and convolution voltammetry of Zr4+|Zr2+ couple in molten LiCl–KCl eutectic

Cited by 41 publications

References 25 publications

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Electrochemical Properties and Analyses of CeCl₃in LiCl-KCl Eutectic Salt

International developments in electrorefining technologies for pyrochemical processing of spent nuclear fuels

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Anodic dissolution of U, Zr and U–Zr alloy and convolution voltammetry of Zr4+|Zr2+ couple in molten LiCl–KCl eutectic

Cited by 41 publications

References 25 publications

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Investigation on the reaction progress of zirconium and cuprous chloride in the LiCl–KCl melt

Electrochemical Properties and Analyses of CeCl3in LiCl-KCl Eutectic Salt

International developments in electrorefining technologies for pyrochemical processing of spent nuclear fuels

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Product

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Electrochemical Properties and Analyses of CeCl₃in LiCl-KCl Eutectic Salt