1971•Unpublished venueOpen access
CHEMICAL ENGINEERING DIVISION FUEL CYCLE TECHNOLOGY QUARTERLY REPORT, JANUARY--MARCH 1971.
Ill. Argonne National Lab., D Webster, A Jonke, G Bernstein, N Levitz, R Pierce, M Steindler, R Vogel
Open full text 1 citations
Abstract
Page 1-1.Head-end Molten Metal-Salt Process Employing a High-Zinc Reduction Alloy 16 1-2.Head-end Molten Metal-Salt Process Employing a Low-Zinc Reduction Alloy 17 1-3.Contents of Crucible after Run SSMD-7 23 1-4.Contents of Crucible 'after Run SSMD-8 23 1-5.Contents of Crucible after Run SSMD-17 23 II-l.Scan of a Diameter of a 0.25-in.-diaU0 2 -PuO" Pellet with an Electron Microprobe 27 II-2.Electron Microprobe Scan of a 0.25-in.-diaUO 2 ~20% Pu0 2 Pellet 29 II-3.Effect of Nitric Acid Concentration on the Crystallization Temperature of Plutonium Nitrate-Uranium Nitrate-Nitric Acid Solutions 32 II-4.Effect of Increasing Plutonium Content upon the Crystallization Temperatures for Uranium-Plutonium Solutions 33 II-5.Crystallization Temperatures of Uranyl Nitrate-Plutonium Nitrate-Nitric Acid Solutions.Effect of Plutonium Cone. at 1.6M Uranyl Nitrate-2M Nitric Acid 34 IV-1.Centrifugal Contactor Assembly 44 IV-2.Rotor and Removable Mixing Paddle 45 V-l.Current-Voltage Curves for Plutonium Ions in 1M HCIO^ . .50 V-2.Conceptual Scheme for Electrolytic Plutonium Valence Adjustment with Centrifugal Contactors 54 V-3.Schematic Drawing of Reduction Cell 61 V-4.Data for Heating and Cooling Air Flowing Normal to Single Cylinders, Corrected for Radiation to Surroundings ... 67 LIST OF TABLES No. • Title Page 1-1.UO_ Reduction Runs 18 1-2.Solubility of Uranium in Zn-Mg-Ca at 800°C 21 II-l.Crystallization Temperatures in the Uranyl Nitrate-Plutonium Nitrate-Nitric Acid System 31 III-l.X-Ray Critical-Absorption and Emission Energies in keV .37 IV-1.