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Electrochemical reduction of high dense UO2 pellets (95% TD) was carried out in molten CaCl2-48mol% NaCl at 923 K by constant voltage and constant current modes of electrolysis using graphite as the anode with an aim to check the feasibility of reduction and to determine the reduction mechanism. Electro-reduction experiments were carried out at 3.3 V for different durations of time (6, 12, 19, 25, 35 and 44 h) in order to obtain partially reduced samples. The UO2 pellets electrolysed for 35 h and above were fully reduced whereas those samples electrolysed for lower durations of time showed only surface reduction. Low current galvanostatic electrolysis of UO2 pellet showed gradual polarization of the cathode to higher cathodic values with time within a band of +0.250 V and 0.000 V vs (Na-Ca)/(Na+,Ca2+). No ternary intermediate compounds of the type Ca-U-O or Na-U-O or sub-oxides were observed in the partially reduced samples. Unlike in pure CaCl2 melt at 1173 K, the consumption of graphite anode and the carbon contamination of the melt were found to be minimum in the present study. Based on the experimental data, a probable mechanism of electrochemical reduction of UO2 to U in molten CaCl2-48mol% NaCl has been proposed.
Electrochemical reduction of high dense UO2 pellets (95% TD) was carried out in molten CaCl2-48mol% NaCl at 923 K by constant voltage and constant current modes of electrolysis using graphite as the anode with an aim to check the feasibility of reduction and to determine the reduction mechanism. Electro-reduction experiments were carried out at 3.3 V for different durations of time (6, 12, 19, 25, 35 and 44 h) in order to obtain partially reduced samples. The UO2 pellets electrolysed for 35 h and above were fully reduced whereas those samples electrolysed for lower durations of time showed only surface reduction. Low current galvanostatic electrolysis of UO2 pellet showed gradual polarization of the cathode to higher cathodic values with time within a band of +0.250 V and 0.000 V vs (Na-Ca)/(Na+,Ca2+). No ternary intermediate compounds of the type Ca-U-O or Na-U-O or sub-oxides were observed in the partially reduced samples. Unlike in pure CaCl2 melt at 1173 K, the consumption of graphite anode and the carbon contamination of the melt were found to be minimum in the present study. Based on the experimental data, a probable mechanism of electrochemical reduction of UO2 to U in molten CaCl2-48mol% NaCl has been proposed.
The article contains sections titled: 1. Introduction 2. History 3. Physical Properties 3.1. Radioactivity 3.2. Modifications 3.3. Mechanical Properties 3.4. Thermal Properties 3.5. Electrical and Electrochemical Properties 3.6. Magnetic Properties 4. Chemical Properties 5. Occurrence, Requirement, and Production Figures 5.1. Occurrence 5.2. Resources, Requirement, and Production Figures 6. Production 6.1. Uses of Uranium and Uranium Compounds 6.2. From Ore to End Product‐A Review of Processes 6.2.1. From Crude Ore to Yellow Cake 6.2.2. From Yellow Cake to UF 6 6.2.3. From UF 6 to the Nuclear Fuel UO 2 6.3. Detailed Description of the Processes 6.3.1. Digestion and Leaching of Ores 6.3.1.1. Acidic Ores 6.3.1.2. Alkaline Ores 6.3.1.3. Digestion of Phosphate Rock 6.3.2. Treatment of the Liquor 6.3.2.1. Uranium Recovery by Ion Exchange 6.3.2.2. Uranium Recovery by Solvent Extraction 6.3.2.3. Eluex Process 6.3.3. Production of Uranium Ore Concentrate 6.3.3.1. From Precipitation to Yellow Cake Production 6.3.3.2. Processing of Phosphate Liquor and Precipitation of AUC 6.3.4. Final Purification of Uranium Concentrate 6.3.4.1. Dissolution of Yellow Cake 6.3.4.2. Extractive Purification 6.3.5. Production of UO 3 and UO 2 from Purified Uranyl Nitrate Solution 6.3.5.1. Evaporation of Uranyl Nitrate Solution and Denitration by Thermal Decomposition 6.3.5.2. Precipitation of Uranium by the ADU and AUC Processes 6.3.5.3. Reduction of Precipitated Product to UO 2 Powder 6.3.6. Production of UF 4 6.3.6.1. Hydrofluorination of UO 2 6.3.6.2. Hydration and Hydrofluorination of UO 3 6.3.7. Production of UF 6 from UF 4 6.3.7.1. Process Description 6.3.7.2. Chemical Reactors 6.3.7.3. Removal of Excess Fluorine from UF 6 6.3.8. Complete Plant for Production of UF 6 from Uranyl Nitrate 6.3.8.1. French Process in Pierrelatte 6.3.8.2. Allied Chemical Process 6.3.9. Enrichment of 235 U 6.3.9.1. Diffusion Process 6.3.9.2. Ultracentrifuges 6.3.9.3. Nozzle Process 6.3.9.4. Chemical Enrichment 6.3.9.5. Laser Separation Process 6.3.9.6. Plasma Processes 6.3.10. Production of UO 2 Pellets from UF 6 6.3.10.1. Conversion of UF 6 to UO 2 6.3.10.2. Possible Future Developments in the Conversion of UF 6 to UO 2 Powder 6.3.10.3. Pelletizing of UO 2 Powder 6.3.11. Production of Uranium Metal 6.3.11.1. Reduction of UF 6 to UF 4 6.3.11.2. Reduction of UF 4 to Uranium Metal 6.3.11.3. Production of Uranium Powder 7. Uranium Alloys 7.1. Classification 7.2. Production of Important Alloys 8. Uranium Compounds 8.1. Halides 8.1.1. Trivalent Halides 8.1.2. Uranium Tetrahalides 8.1.3. Uranium Pentafluoride 8.1.4. Uranium Hexafluoride 8.2. Carbides 8.3. Nitrides 8.4. Oxides 8.4.1. Uranium Dioxide 8.4.2. Uranium Trioxide 8.4.3. Triuranium Octaoxide 8.4.4. Peroxides 8.5. Nitrates, Sulfates, and the Carbonato Complex 8.5.1. Nitrates 8.5.2. Sulfates 8.5.3. Tricarbonatodioxouranate 9. Safety 9.1. Radiation Shielding 9.2. Safety Against Uncontrolled Criticality 9.3. Geometrically Safe Vessels 9.4. Apparatus with Heterogeneous Neutron Absorbers
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