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荒井 陽一; 渡部 創; 大野 真平; 野村 和則; 中村 文也*; 新井 剛*; 瀬古 典明*; 保科 宏行*; 羽倉 尚人*; 久保田 俊夫*
Nuclear Instruments and Methods in Physics Research B, 477, p.54 - 59, 2020/08
被引用回数：7 パーセンタイル：57.03(Instruments & Instrumentation)Used PUREX process solvent generated from reprocessing process of spent nuclear fuel contains a small amount of U and Pu complexed with tributyl phosphate (TBP) or dibutyl phosphate (DBP). The radioactive nuclides should be removed from the solvent for safety storage or disposal. The iminodiacetic acid (IDA) type chelating resin was proposed as promising procedures for efficient recovery of the trapped cations in the solvent. In order to reveal the distribution and amount of Zr in the particle and local structure of Zr complex formed in the adsorbent, PIXE and EXAFS analyses on the Zr adsorbed chelating resin were carried out. Micro-PIXE analysis proved that it is an effectual method for quantitative analysis of trace adsorbed elements. Moreover, some of the adsorption sites were possibly occupied by the molecules. On the other hand, Zr-K edge EXAFS analysis suggested that extraction mechanism of Zr from the aqueous solution and the solvent was different.
荒井 陽一; 渡部 創; 大野 真平; 野村 和則; 中村 文也*; 新井 剛*; 瀬古 典明*; 保科 宏行*; 久保田 俊夫*
QST-M-23; QST Takasaki Annual Report 2018, P. 59, 2020/03
Radioactive spent solvent waste contains U and Pu is generated from reprocessing process of spent nuclear fuel. The nuclear materials should be removed from the solvent for safety storage or disposal. We are focusing on the nuclear materials recovery from spent solvent using imino diacetic acid (IDA) type chelating resin as a promising method. In order to reveal adsorbed amount of Zr, which is simulated of Pu, Micro-Particle Induced X-ray Emission (PIXE) was carried out. Micro-PIXE analysis succeeded in quantitative analysis on trace amount of adsorbed Zr from simulated spent solvent.
中村 文也*; 安倍 諒治*; 新井 剛*; 瀬古 典明*; 荒井 陽一; 渡部 創; 野村 和則
no journal, ,
It is considered that tributyl phosphate (TBP) contained in spent PUREX solvent is well known to decompose into dibutyl phosphate (DBP) by radiation exposure. It has been found that DBP extracts U and Pu to form strong complexes. Since these complexes have stability even at low nitric acid solution, the spent solvent loaded with U and Pu for a long term is difficult to back extracted using nitric solution. Therefore, we have studied the treatment method for adsorbing of U and Pu from spent solvent using adsorbent. In this study, the method of Zr(IV) quantitative analysis using fluorescence spectroscopy was established. Moreover, adsorption behavior of Zr(IV) in DSP-n using adsorbents was evaluated. It was confirmed that non-woven fabrics with phosphoric acid type and imino diacetic acid type showed excellent adsorption ability.
