Development of Spent Solvent Treatment Process by a Submerged Combustion Technique.

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概要

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• An experimental study using a bench-scale equipment of 1 kg-simulated spent solvents per hour has been conducted in order to evaluate the applicability of a submerged combustion technique to the treatment of spent solvents contaminated with TRU elements. <BR>This report describes the experimental results on the combustion characteristics of the simulated spent solvents of tri-n-butyl phosphate and/or n-dodecane, and on the distribution behaviors of combustion products such as phosphoric acid, Ru, I, Zr and lanthanides as TRU simulants in the submerged combustion process. Also the experimental results of TRU separation from phosphoric acid solution by co-precipitation using bismuth phosphate are reported. <BR>It was shown that the submerged combustion technique was applicable to the treatment of spent solvents including the distillation residues of the solvent. Based on the experimental data, a new treatment process of spent solvent was proposed which consisted of submerged combustion, co-precipitation using bismuth phosphate, ceramic membrane filtration, cementation of TRU lean phosphate, and vitrification of TRU rich waste.

• 一般社団法人 日本原子力学会の論文

著者

• Uchiyama Gunzo

  Department Of Fuel Cycle Safety Japan Atomic Energy Research Institute

• Fujine Sachio

  Department Of Fuel Cycle Safety Japan Atomic Energy Research Institute

• FUJINE Sachio

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

• MAEDA Mitsuru

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

• AMAKAWA Masayuki

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

• UCHIDA Katsuhide

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

• CHIDA Mitsuhisa

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

• UCHIYAMA Gunzo

  Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

関連論文

• An Investigation into Dissolution Rate of Spent Nuclear Fuel in Aqueous Reprocessing
• Prearation of Novel Silica-Based Nitrogen Donor Extraction Resins and Their Adsorption Performance for Trivalent Americium adn Lanthanides
• Analysis of a Uranium Solution for Evaluating the Total Number of Fissions in the JCO Criticality Accident in Tokai-mura
• Development of Spent Solvent Treatment Process by a Submerged Combustion Technique.

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