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J P Glatz - One of the best experts on this subject based on the ideXlab platform.
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zirconium behaviour during Electrorefining of actinide zirconium alloy in molten licl kcl on aluminium cathodes
Journal of Nuclear Materials, 2016Co-Authors: Roland Meier, Pavel Soucek, Rikard Malmbeck, Michael Krachler, A Rodrigues, Benoit Claux, J P Glatz, Th FanghanelAbstract:Abstract A pyrochemical Electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An–Zr) in a molten salt is being investigated. In this process actinides are group-selectively recovered on solid aluminium cathodes as An–Al alloys using a LiCl–KCl eutectic melt at a temperature of 450 °C. In the present study the electrochemical behaviour of zirconium during Electrorefining was investigated. The maximum amount of actinides that can be oxidised without anodic co-dissolution of zirconium was determined at a selected constant cathodic current density. The experiment consisted of three steps to assess the different stages of the Electrorefining process, each of which employing a fresh aluminium cathode. The results indicate that almost a complete dissolution of the actinides without co-dissolution of zirconium is possible under the applied experimental conditions.
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separation of actinides from irradiated an zr based fuel by Electrorefining on solid aluminium cathodes in molten licl kcl
Journal of Nuclear Materials, 2015Co-Authors: Pavel Soucek, Roland Meier, Rikard Malmbeck, Benoit Claux, T Murakami, Takeshi Tsukada, J P GlatzAbstract:Abstract An Electrorefining process for metallic spent nuclear fuel treatment is being investigated in ITU. Solid aluminium cathodes are used for homogeneous recovery of all actinides within the process carried out in molten LiCl–KCl eutectic salt at a temperature of 500 °C. As the selectivity, efficiency and performance of solid Al has been already shown using un-irradiated An–Zr alloy based test fuels, the present work was focused on laboratory-scale demonstration of the process using irradiated METAPHIX-1 fuel composed of U 67 –Pu 19 –Zr 10 –MA 2 –RE 2 (wt.%, MA = Np, Am, Cm, RE = Nd, Ce, Gd, Y). Different Electrorefining techniques, conditions and cathode geometries were used during the experiment yielding evaluation of separation factors, kinetic parameters of actinide–aluminium alloy formation, process efficiency and macro-structure characterisation of the deposits. The results confirmed an excellent separation and very high efficiency of the Electrorefining process using solid Al cathodes.
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Electrorefining of u pu zr alloy fuel onto solid aluminium cathodes in molten licl kcl
Radiochimica Acta, 2008Co-Authors: Pavel Soucek, Rikard Malmbeck, Laurent Cassayre, Eric Mendes, Regis Jardin, J P GlatzAbstract:An Electrorefining process in molten chloride salts using solid aluminium cathodes is being developed at ITU to recover actinides (An) from the spent nuclear fuel. The maximum possible loading of aluminium electrodes with actinides was investigated during the Electrorefining of UPuZr alloy in a LiCl-KCl eutectic at 450°C. Two different electrolytic techniques were applied during the experiment and almost 6000 C has been passed, corresponding to 3.7 g of deposited actinides. A very high capacity of aluminium to retain actinides has been proven as the average Al:An mass ratio was 1:1.58 for galvanostatic and 1:2.25 for potentiostatic mode. The obtained deposits were characterized by XRD and SEM-EDX analysis and alloys composed of (U,Pu)Al3 were detected. The influence of zirconium co-oxidation during the process was also investigated and the presence of dissolved Zr ions in the melt yielded a significant deterioration of the quality of the deposit.
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separation of actinides from rare earth elements by means of molten salt Electrorefining with anodic dissolution of u pu zr alloy fuel
Journal of Physics and Chemistry of Solids, 2005Co-Authors: Kensuke Kinoshita, Tadafumi Koyama, Tadashi Inoue, Michel Ougier, J P GlatzAbstract:Abstract Electrorefining is the main process for pyro-reprocessing of the fuel of a metallic fuel FBR. To obtain a basic knowledge of Electrorefining technology, a series of experiments was carried out with unirradiated fuel alloy. The alloy, 71U–19Pu–10Zr (wt.%), was dissolved anodically into a molten LiCl–KCl bath at 753 K. Simultaneously, Pu and U were recovered into the Cd cathode with small amounts of minor actinides, Zr and rare earth elements (REs). The separation factors of U, Np, Am, Cm and Ce against Pu, derived from the composition of recovered deposits and of the salt bath, were about 2.04, 0.949, 0.597, 0.534 and 0.0393, respectively, which are similar to the equilibrium values observed in a distribution experiment in a LiCl–KCl/Cd system. This demonstrates that Electrorefining achieves the separation of actinides from REs. The anodic dissolution of the alloy was found to progress from the outside, leaving a dense layer containing salt and Zr metal around the alloy surface. It was found that more than 99.9% of both U and Pu could be dissolved from the alloy and about 55% of Zr remained in this layer.
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study of molten salt Electrorefining of u pu zr alloy fuel
Journal of Nuclear Science and Technology, 2002Co-Authors: Tadafumi Koyama, J P Glatz, Tadashi Inoue, Michel Ougier, Kensuke Kinosmta, Rlkard Malmbeck, Lothar KochAbstract:Electrorefining of unirradiated metal alloy fuel, U-20Pu-10Zr (% by weight), was carried out in an Ar atmosphere cell to obtain a basic knowledge of spent fuel treatment. Before Electrorefining, the Pu ion concentration in LiCl-KCl electrolyte was adjusted to 4 wt.% using pure Pu metal and CdCl2. Cylindrical alloy fuel was anodically dissolved in the salt electrolyte. Electrotransport to either liquid Cd cathode or solid cathode was carried out several times in galvanic mode. The deposit on the solid cathode mostly consisted of metal U and entrained salt and took place at high current efficiency. The recovery of Pu and Am into a liquid cadmium cathode was also demonstrated with high current efficiency. The anodic dissolution of the fuel alloy was found to progress from the outside whilst leaving a dense salt layer on the alloy surface. The peculiar fluctuation of anode potential during U-Pu-Zr dissolution was explained by the competitive oxidation of U-Pu and Zr.
Tadashi Inoue - One of the best experts on this subject based on the ideXlab platform.
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separation of actinides from rare earth elements by means of molten salt Electrorefining with anodic dissolution of u pu zr alloy fuel
Journal of Physics and Chemistry of Solids, 2005Co-Authors: Kensuke Kinoshita, Tadafumi Koyama, Tadashi Inoue, Michel Ougier, J P GlatzAbstract:Abstract Electrorefining is the main process for pyro-reprocessing of the fuel of a metallic fuel FBR. To obtain a basic knowledge of Electrorefining technology, a series of experiments was carried out with unirradiated fuel alloy. The alloy, 71U–19Pu–10Zr (wt.%), was dissolved anodically into a molten LiCl–KCl bath at 753 K. Simultaneously, Pu and U were recovered into the Cd cathode with small amounts of minor actinides, Zr and rare earth elements (REs). The separation factors of U, Np, Am, Cm and Ce against Pu, derived from the composition of recovered deposits and of the salt bath, were about 2.04, 0.949, 0.597, 0.534 and 0.0393, respectively, which are similar to the equilibrium values observed in a distribution experiment in a LiCl–KCl/Cd system. This demonstrates that Electrorefining achieves the separation of actinides from REs. The anodic dissolution of the alloy was found to progress from the outside, leaving a dense layer containing salt and Zr metal around the alloy surface. It was found that more than 99.9% of both U and Pu could be dissolved from the alloy and about 55% of Zr remained in this layer.
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study of molten salt Electrorefining of u pu zr alloy fuel
Journal of Nuclear Science and Technology, 2002Co-Authors: Tadafumi Koyama, J P Glatz, Tadashi Inoue, Michel Ougier, Kensuke Kinosmta, Rlkard Malmbeck, Lothar KochAbstract:Electrorefining of unirradiated metal alloy fuel, U-20Pu-10Zr (% by weight), was carried out in an Ar atmosphere cell to obtain a basic knowledge of spent fuel treatment. Before Electrorefining, the Pu ion concentration in LiCl-KCl electrolyte was adjusted to 4 wt.% using pure Pu metal and CdCl2. Cylindrical alloy fuel was anodically dissolved in the salt electrolyte. Electrotransport to either liquid Cd cathode or solid cathode was carried out several times in galvanic mode. The deposit on the solid cathode mostly consisted of metal U and entrained salt and took place at high current efficiency. The recovery of Pu and Am into a liquid cadmium cathode was also demonstrated with high current efficiency. The anodic dissolution of the fuel alloy was found to progress from the outside whilst leaving a dense salt layer on the alloy surface. The peculiar fluctuation of anode potential during U-Pu-Zr dissolution was explained by the competitive oxidation of U-Pu and Zr.
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measurement of standard potentials of actinides u np pu am in licl kcl eutectic salt and separation of actinides from rare earths by Electrorefining
Journal of Alloys and Compounds, 1998Co-Authors: Yoshiharu Sakamura, Kensuke Kinoshita, Tadashi Inoue, D. L. Grimmett, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, S. P. FusselmanAbstract:Abstract Pyrochemical separation of actinides from rare earths in LiCl–KCl eutectic–liquid metal systems has been studied. The electromotive forces of galvanic cells of the form, Ag|Ag(I), LiCl–KCl‖actinide(III), LiCl–KCl|actinide, were measured and standard potentials were determined for uranium, neptunium and plutonium to be −1.283 V, −1.484 V and −1.593 V (at 450°C vs. Ag/AgCl (1wt%–AgCl)), respectively. A typical cyclic voltammogram of americium chloride has two cathodic peaks, which suggests reduction Am(III)→Am(II) occurs followed by reduction of Am(II) to americium metal. Standard potential of Am(II)/Am(0) was estimated to be −1.642 V. Electrorefining experiments to separate actinides (U, Np, Pu and Am) from rare earths (Y, La, Ce, Nd and Gd) in LiCl–KCl eutectic salt were carried out. It was shown that the actinide metals were recovered on the cathodes and that americium was the most difficult to separate from rare earths. The actinide separation will be achieved by means of the combination of Electrorefining with multistage extraction.
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separation of actinides from rare earth elements by Electrorefining in licl kcl eutectic salt
Journal of Nuclear Science and Technology, 1998Co-Authors: Kensuke Kinoshita, Tadashi Inoue, S. P. Fusselman, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, Yoshiharu Sakamura, L F Grantham, D. L. GrimmettAbstract:A pyrometallurgical partitioning technology to recover actinides from high level radioactive wastes is being developed. In the process, actinides are separated from fission products by Electrorefining in molten chloride systems. It is expected that REs (rare earth elements), main components of fission products are hardly separated from actinides. In order to estimate separation factors, Electrorefining experiments to recover actinides from LiCl-KCl eutectic salt containing actinide (U, Np, Pu and Am) and RE (Y, La, Ce, Nd and Gd) chlorides were carried out at 450°C. Actinides were removed from a liquid cadmium anode and recovered as metal on a solid cathode. Typical cathode deposits were rough in appearance and contained 70-90wt% adhering salt. The current efficiency was low because some of the deposit occasionally fell from the cathode. It is shown that uranium, neptunium and plutonium are relatively easily separated from REs and that americium is accompanied by some of REs.
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Separation of actinides from lanthanides utilizing molten salt Electrorefining
1996Co-Authors: D. L. Grimmett, Tadashi Inoue, S. P. Fusselman, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, Noriaki TakahashiAbstract:TRUMP-S (TRansUranic Management through Pyropartitioning Separation) is a pyrochemical process being developed to separate actinides form fission products in nuclear waste. A key process step involving molten salt Electrorefining to separate actinides from lanthanides has been studied on a laboratory scale. Electrorefining of U, Np, Pu, Am, and lanthanide mixtures from molten cadmium at 450 C to a solid cathode utilizing a molten chloride electrolyte resulted in > 99% removal of actinides from the molten cadmium and salt phases. Removal of the last few percent of actinides is accompanied by lowered cathodic current efficiency and some lanthanide codeposition. Actinide/lanthanide separation ratios on the cathode are ordered U > Np > Pu > Am and are consistent with predictions based on equilibrium potentials.
Yoshiharu Sakamura - One of the best experts on this subject based on the ideXlab platform.
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electrolytic reduction and Electrorefining of uranium to develop pyrochemical reprocessing of oxide fuels
Nuclear Technology, 2010Co-Authors: Yoshiharu Sakamura, Takashi OmoriAbstract:AbstractTwo series of pyrochemical reprocessing tests for oxide fuels, consisting of pretreatment, electrolytic reduction, and Electrorefining processes, were conducted using ~100 g of UO2. In the pretreatment process, UO2 pellets of the starting material were oxidized into U3O8 powder, which simulated fuel decladding by voloxidation. Then, UO2 sinter with a porosity of 30 to 38% was fabricated from the U3O8 powder. Two cathode baskets charged with ~100 g of the UO2 sinter were prepared, and two electrolytic reduction tests were carried out in a LiCl-Li2O electrolyte at 650°C. The results suggested that the reduction to uranium metal could be completed within 10 h with the current efficiency >62%. It was verified that the porous UO2 sinter was of great advantage to the electrolytic reduction process. In the subsequent Electrorefining process, the reduction products were charged in two anode baskets, and electrolysis was carried out in a LiCl-KCl-UCl3 electrolyte at 500°C. Within 8 h, most of the uranium m...
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measurement of standard potentials of actinides u np pu am in licl kcl eutectic salt and separation of actinides from rare earths by Electrorefining
Journal of Alloys and Compounds, 1998Co-Authors: Yoshiharu Sakamura, Kensuke Kinoshita, Tadashi Inoue, D. L. Grimmett, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, S. P. FusselmanAbstract:Abstract Pyrochemical separation of actinides from rare earths in LiCl–KCl eutectic–liquid metal systems has been studied. The electromotive forces of galvanic cells of the form, Ag|Ag(I), LiCl–KCl‖actinide(III), LiCl–KCl|actinide, were measured and standard potentials were determined for uranium, neptunium and plutonium to be −1.283 V, −1.484 V and −1.593 V (at 450°C vs. Ag/AgCl (1wt%–AgCl)), respectively. A typical cyclic voltammogram of americium chloride has two cathodic peaks, which suggests reduction Am(III)→Am(II) occurs followed by reduction of Am(II) to americium metal. Standard potential of Am(II)/Am(0) was estimated to be −1.642 V. Electrorefining experiments to separate actinides (U, Np, Pu and Am) from rare earths (Y, La, Ce, Nd and Gd) in LiCl–KCl eutectic salt were carried out. It was shown that the actinide metals were recovered on the cathodes and that americium was the most difficult to separate from rare earths. The actinide separation will be achieved by means of the combination of Electrorefining with multistage extraction.
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separation of actinides from rare earth elements by Electrorefining in licl kcl eutectic salt
Journal of Nuclear Science and Technology, 1998Co-Authors: Kensuke Kinoshita, Tadashi Inoue, S. P. Fusselman, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, Yoshiharu Sakamura, L F Grantham, D. L. GrimmettAbstract:A pyrometallurgical partitioning technology to recover actinides from high level radioactive wastes is being developed. In the process, actinides are separated from fission products by Electrorefining in molten chloride systems. It is expected that REs (rare earth elements), main components of fission products are hardly separated from actinides. In order to estimate separation factors, Electrorefining experiments to recover actinides from LiCl-KCl eutectic salt containing actinide (U, Np, Pu and Am) and RE (Y, La, Ce, Nd and Gd) chlorides were carried out at 450°C. Actinides were removed from a liquid cadmium anode and recovered as metal on a solid cathode. Typical cathode deposits were rough in appearance and contained 70-90wt% adhering salt. The current efficiency was low because some of the deposit occasionally fell from the cathode. It is shown that uranium, neptunium and plutonium are relatively easily separated from REs and that americium is accompanied by some of REs.
S. P. Fusselman - One of the best experts on this subject based on the ideXlab platform.
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measurement of standard potentials of actinides u np pu am in licl kcl eutectic salt and separation of actinides from rare earths by Electrorefining
Journal of Alloys and Compounds, 1998Co-Authors: Yoshiharu Sakamura, Kensuke Kinoshita, Tadashi Inoue, D. L. Grimmett, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, S. P. FusselmanAbstract:Abstract Pyrochemical separation of actinides from rare earths in LiCl–KCl eutectic–liquid metal systems has been studied. The electromotive forces of galvanic cells of the form, Ag|Ag(I), LiCl–KCl‖actinide(III), LiCl–KCl|actinide, were measured and standard potentials were determined for uranium, neptunium and plutonium to be −1.283 V, −1.484 V and −1.593 V (at 450°C vs. Ag/AgCl (1wt%–AgCl)), respectively. A typical cyclic voltammogram of americium chloride has two cathodic peaks, which suggests reduction Am(III)→Am(II) occurs followed by reduction of Am(II) to americium metal. Standard potential of Am(II)/Am(0) was estimated to be −1.642 V. Electrorefining experiments to separate actinides (U, Np, Pu and Am) from rare earths (Y, La, Ce, Nd and Gd) in LiCl–KCl eutectic salt were carried out. It was shown that the actinide metals were recovered on the cathodes and that americium was the most difficult to separate from rare earths. The actinide separation will be achieved by means of the combination of Electrorefining with multistage extraction.
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separation of actinides from rare earth elements by Electrorefining in licl kcl eutectic salt
Journal of Nuclear Science and Technology, 1998Co-Authors: Kensuke Kinoshita, Tadashi Inoue, S. P. Fusselman, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, Yoshiharu Sakamura, L F Grantham, D. L. GrimmettAbstract:A pyrometallurgical partitioning technology to recover actinides from high level radioactive wastes is being developed. In the process, actinides are separated from fission products by Electrorefining in molten chloride systems. It is expected that REs (rare earth elements), main components of fission products are hardly separated from actinides. In order to estimate separation factors, Electrorefining experiments to recover actinides from LiCl-KCl eutectic salt containing actinide (U, Np, Pu and Am) and RE (Y, La, Ce, Nd and Gd) chlorides were carried out at 450°C. Actinides were removed from a liquid cadmium anode and recovered as metal on a solid cathode. Typical cathode deposits were rough in appearance and contained 70-90wt% adhering salt. The current efficiency was low because some of the deposit occasionally fell from the cathode. It is shown that uranium, neptunium and plutonium are relatively easily separated from REs and that americium is accompanied by some of REs.
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Separation of actinides from lanthanides utilizing molten salt Electrorefining
1996Co-Authors: D. L. Grimmett, Tadashi Inoue, S. P. Fusselman, C. L. Krueger, T. S. Storvick, Takatoshi Hijikata, Noriaki TakahashiAbstract:TRUMP-S (TRansUranic Management through Pyropartitioning Separation) is a pyrochemical process being developed to separate actinides form fission products in nuclear waste. A key process step involving molten salt Electrorefining to separate actinides from lanthanides has been studied on a laboratory scale. Electrorefining of U, Np, Pu, Am, and lanthanide mixtures from molten cadmium at 450 C to a solid cathode utilizing a molten chloride electrolyte resulted in > 99% removal of actinides from the molten cadmium and salt phases. Removal of the last few percent of actinides is accompanied by lowered cathodic current efficiency and some lanthanide codeposition. Actinide/lanthanide separation ratios on the cathode are ordered U > Np > Pu > Am and are consistent with predictions based on equilibrium potentials.
Moriyasu Tokiwai - One of the best experts on this subject based on the ideXlab platform.
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Investigation of Cell Resistance for Molten Salt Electrorefining of Spent Nuclear Fuel
Journal of Nuclear Science and Technology, 1995Co-Authors: Tsuguyuki Kobayashi, Moriyasu TokiwaiAbstract:Cell resistance for molten salt Electrorefining of spent nuclear fuel under various electrode configurations was investigated by using the two-dimensional finite element method. Three Electrorefining cell configurations were evaluated; (1) a liquid Cd anode and a solid cathode made of low carbon steel with or without a ceramic plate at the bottom, (2) a liquid Cd anode and a liquid Cd cathode, and (3) two anodes in the form of a perforated steel basket filled with spent nuclear fuel and two solid cathodes, in two different arrangements. The calculated results agreed reasonably well with previously obtained experimental data. The effect of polarization on the cell resistance was found to be small for a typical uranium concentration in the molten salt electrolyte and the liquid Cd anode. The calculation results are helpful in interpreting experimental data, and a correlation formula was developed that may be useful in estimating the cell resistance of new cell designs.
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development of trail a simulation code for the molten salt Electrorefining of spent nuclear fuel
Journal of Alloys and Compounds, 1993Co-Authors: Tsuguyuki Kobayashi, Moriyasu TokiwaiAbstract:Abstract A simulation code for the molten salt Electrorefining of spent metallic nuclear fuel from the Integral Fast Reactor has been developed. This code (named trail ) employs diffusion layer theory in the vicinity of the electrodes. Model parameters such as the diffusion layer thickness were determined from polarization data measured with uranium at different concentrations in the molten salt electrolyte and liquid cadmium anode of an Electrorefining cell. Calculations were made to verify the code with experimental data for various operational modes. Good agreement with the data was obtained. It was also found that this code can provide useful information to aid in understanding the electrotransport process within the electrorefiner.