Batch Crystallization of Uranyl Nitrate
スポンサーリンク
概要
- 論文の詳細を見る
Batch crystallization of uranyl nitrate is carried out in order to obtain fundamental data required for the development of reprocessing involving crystallization. Particular attention is paid to the development of a method for predicting the concentrations of uranium and nitric acid in the mother liquor and the amount of uranyl nitrate crystals produced. Initial concentrations of uranyl nitrate and nitric acid are 500–600 g/l and 4–6 mol/l, respectively, corresponding to the condition of a dissolver solution of spent fuel. Steady-state mass balance equations including the correlation equation for the equilibrium solubility of uranium nitrate are applied to the prediction. The calculated concentrations of uranium and nitric acid are in close agreement with the experimental ones. The recovery of uranium is accurately predicted by the calculated concentrations, with an error of less than 10%.
- 社団法人 日本原子力学会の論文
- 2008-06-01
著者
-
Kikuchi Toshiaki
Energy Project And Technol. Center Mitsubishi Materials Corp.
-
Homma Shunji
Division Of Materials Science Graduate School Of Science And Engineering Saitama University
-
Koyama Tomozo
Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency
-
Kikuchi Toshiaki
Energy Project And Technology Center Mitsubishi Materials Corporation
-
SHIBATA Atsuhiro
Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency
-
CHIKAZAWA Takahiro
Energy Project and Technology Center, Mitsubishi Materials Corporation
-
Chikazawa Takahiro
Energy Project And Technology Center Mitsubishi Materials Corporation
-
Shibata Atsuhiro
Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency
-
Homma Shunji
Div. Of Materials Sci. Graduate School Of Sci. And Engineering Saitama Univ.
-
Koyama Tomozo
Nuclear Cycle Engineering Department Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency
-
Shibata Atsuhiro
Nuclear Cycle Engineering Department Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency
関連論文
- Development of Advanced Reprocessing System Based on Precipitation Method Using Pyrrolidone Derivatives as Precipitants : Precipitation Behavior of U(VI), Pu(IV), and Pu(VI) by Pyrrolidone Derivatives with Low Hydrophobicity
- Solubility of Uranyl Nitrate Precipitates with N-Alkyl-2-pyrrolidone Derivatives (Alkyl = n-Propyl, n-Butyl, iso-Butyl, and Cyclohexyl
- A Study on Precipitation Behavior of Plutonium and Other Transuranium Elements with N-Cyclohexyl-2-pyrrolidone for Development of a Simple Reprocessing Process
- Anodic Dissolution of UO_2 Pellet Containing Simulated Fission Products in Ammonium Carbonate Solution
- Reaction Model for Fluorination of Uranium Dioxide Using Improved Unreacted Shrinking Core Model for Expanding Spherical Particles
- Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle
- ICONE11-36431 Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle
- Experimental Study on U-Pu Cocrystallization Reprocessing Process
- Batch Crystallization of Uranyl Nitrate
- Flowsheet Study of U-Pu Co-Crystallization Reprocessing System
- Numerical Simulation of Neptunium Extraction Behavior in Co-decontamination Stage for Late Split Purex System
- Computations of the Breakup of a Jet into Drops in Non-Newtonian Liquid-Liquid Systems
- Fluorination Reaction of Uranium Dioxide by Fluorine
- Development of COMPAS, Computer Aided Process Flowsheet Design and Analysis System of Nuclear Fuel Reprocessing
- Separation of Actinide Elements by Solvent Extraction Using Centrifugal Contactors in the NEXT Process
- Uranium Crystallization Test with Dissolver Solution of Irradiated Fuel
- Numerical Simulation of the Formation of a Jet and Droplets from a Capillary in a Co-Flowing Ambient Fluid
- Removal of Liquid and Solid Impurities from Uranyl Nitrate Hexahydrate Crystalline Particles in Crystal Purification Process
- Elongational Viscosities of Entangled Linear Polymers
- Application of Data Reconciliation and Gross Error Detection to Nuclear Material Accounting for Spent Fuel Reprocessing
- Swelling Process of Cylindrical Polymer Gel
- Numerical Calculations of Pattern Formation of Compound Drops Detaching from a Compound Jet in a Co-Flowing Immiscible Fluid
- Nitric Acid Concentration Dependence of Dicesium Plutonium(IV) Nitrate Formation during Solution Growth of Uranyl Nitrate Hexahydrate
- Computations of Compound Droplet Formation from a Co-Axial Dual Nozzle by Three-Fluid Front Tracking Method
- A Front-Tracking Method for Three-Phase Computations of Solidification with Volume Change