Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

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概要

• 論文の詳細を見る

• The design study of an aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems in Japan. A simplified PUREX process, with the addition of a uranium crystallization step and a minor actinide (MA) recovery process was proposed as the NEXT process. For the simplified PUREX process and the SETFICS/TRUEX process for MA recovery, small-scale hot tests were conducted. The test results showed the decontamination factor (DF) of 105 for the U, Pu and Np product was a reasonable target for the simplified PUREX process. Concerning to the Am and Cm product, the DF of rare earth elements (REs) and the other fission products (FPs) were over 10 and over 102, respectively.For economical competitiveness, an aqueous reprocessing plant with the capacity of 200 tHM/yr cleared the target cost, while the plant with the capacity of 50 tHM/yr did not clear it. For efficient utilization of resources, the calculated U and TRU recovery of both plants was over 99 wt%. Using salt-free reagents and repeating concentration of waste solutions, the environmental impact was reduced. Pu was not isolated through the whole processes in the NEXT process in order to keep the proliferation resistance.

• 社団法人 日本原子力学会の論文
• 2004-03-25

著者

• Ogino Hideki

  Tokai Works Japan Nuclear Cycle Development Institute

• TAKATA Takeshi

  O-arai Engineering Center, Japan Nuclear Cycle Development Institute

• KOMA Yoshikazu

  O-arai Engineering Center, Japan Nuclear Cycle Development Institute

• SATO Koji

  O-arai Engineering Center, Japan Nuclear Cycle Development Institute

• KAMIYA Masayoshi

  Tokai Works, Japan Nuclear Cycle Development Institute

• SHIBATA Atsuhiro

  Tokai Works, Japan Nuclear Cycle Development Institute

• NOMURA Kazunori

  Tokai Works, Japan Nuclear Cycle Development Institute

• KOYAMA Tomozo

  Tokai Works, Japan Nuclear Cycle Development Institute

• AOSE Shin-ichi

  Tokai Works, Japan Nuclear Cycle Development Institute

• Aose Shinichi

  Tokai Works Japan Nuclear Cycle Development Institute

• Koyama Tomozo

  Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency

• Takata Takeshi

  O-arai Engineering Center Japan Nuclear Cycle Development Institute

• SHIBATA Atsuhiro

  Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency

• Nomura Kazunori

  Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency

• Shibata Atsuhiro

  Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency

• Sato Koji

  O-arai Engineering Center Japan Nuclear Cycle Development Institute

• Shibata Atsuhiro

  Nuclear Cycle Engineering Department Nuclear Fuel Cycle Engineering Laboratories Japan Atomic Energy Agency

関連論文

• 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
• Separation of Actinide Elements by Solvent Extraction Using Centrifugal Contactors in the NEXT Process
• Uranium Crystallization Test with Dissolver Solution of Irradiated Fuel
• Removal of Liquid and Solid Impurities from Uranyl Nitrate Hexahydrate Crystalline Particles in Crystal Purification Process
• Numerical Simulation of Extraction Behavior of Americium and Nitric Acid in the TRUEX Process
• Nitric Acid Concentration Dependence of Dicesium Plutonium(IV) Nitrate Formation during Solution Growth of Uranyl Nitrate Hexahydrate

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