Development of Transuranium Element Recovery from High-Level Radioactive Liquid Waste Conversion TRU Oxalates to Chlorides

スポンサーリンク

概要

• 論文の詳細を見る

• The separation methods of transuranium elements (TRUs) from high-level radioactive liquid waste (HLW) are classified into two categories, such as the wet processes and dry processes. A new partitioning process which combines the wet process and dry process has been developed by Toshiba Corporation. Figure 1 shows this process which combines oxalate precipitation and electrorefining. The oxalate precipitation yields good TRU recovery and electrorefining gives good TRU separation from HLW. There are three steps in the process. First, TRUs, lanthanides and alkaline earth elements whose oxalates are lower in solubility are recovered from HLW by the addition of oxalic acid. The previous paper<SUP>(1)</SUP> shows the experimental study which satisfies the requirement of 99.9% recovery of simulated TRUs from simulated HLW by the oxalate precipitation. In the second step, theseoxalates are converted to chlorides. In the final step, the TRUs are recovered on a cathode by electrorefining after dissolving the chlorides in eutectic KC1-LiC1 salt.<BR>The TRU oxalates were converted to chlorides by inducing reactions with CoCl<SUB>2</SUB>, HCl or CCl<SUB>4</SUB> at 500 °C<SUP>(2)-(4)</SUP>. The materials of apparatus must be using corrosion resistance at high temperature. Further, it is necessary for tetravalent TRU chlorides such as NpCl<SUB>4</SUB>, whose vapor pressures are high<SUP>(5)</SUP>, to be recovered. Therefore, the conversion from oxalates to chlorides satisfies the requirements of no use of corrosive gas and lower reaction temperature.<BR>This note describes an experimental study to confirm the new partitioning process, which is found to satisfy the requirement for conversion of simulated TRU oxalates to chlorides without corrosive gas and at lower temperature.

• 社団法人 日本原子力学会の論文
• 1996-10-25

著者

• FUJITA Reiko

  Nuclear Engineering Laboratory, Toshiba Corporation

• Akai Yoshie

  Nuclear Engineering Laboratory Toshiba Corp.

• Fujita Reiko

  Nuclear Engineering Laboratory Toshiba Corp.

関連論文

• Electrorefining Experiments to Recover Uranium with a Cadmium-Lithium Anode and Their Theoretical Evaluation
• An Experimental Study of Molten Salt Electrorefining of Uranium Using Solid Iron Cathode and Liquid Cadmium Cathode for Development of Pyrometallurgical Reprocessing
• Evaluation of Cadmium Pool Potential in a Electrorefiner with Ceramic Partition for Spent Metallic Fuel
• Recovery of Ba^ Using Liquid Metallic Cathodes in Molten Chlorides
• Recovery of Caesium Using Liquid Metallic Cathodes in Molten Fluoride System
• Recovery of Eu^ and Sr^Using Liquid Metallic Cathodes in Molten NaC1-KC1 and KC1 System
• Development of Transuranium Element Recovery from High-Level Rdaioactive Liquid Waste
• Enrichment of Fission Products in Ionic Salt Bath by Countercurrent Electromigration
• Development of Transuranium Element Recovery from High-Level Radioactive Liquid Waste Conversion TRU Oxalates to Chlorides

スポンサーリンク