Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (5): 62 doi: 10.1007/s41365-017-0214-y

• NUCLEAR CHEMISTRY,RADIOCHEMISTRY,RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE • Previous Articles     Next Articles

Th(IV) and U(VI) removal by TODGA in ionic liquids: extraction behavior and mechanism, and radiation effect

Zhen Dong1,2 • Wei-Jin Yuan1,2 • Chao Liu1 • Long Zhao1,2 • Chao Zhao3 • Fang-Dong Tang3 • Lin-Feng He3   

  1. 1 Non-power Nuclear Technology Collaborative Innovation Center, School of Nuclear Technology and Chemistry & Biology, Hubei University of Science and Technology, Xianning 437100, China
    2 School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
    3 Division of Chemistry and Ionizing Radiation Measurement Technology, Shanghai Institute of Measurement and Testing Technology, Shanghai 201203, China
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Zhen Dong, Wei-Jin Yuan, Chao Liu, Long Zhao, Chao Zhao, Fang-Dong Tang, Lin-Feng He. Th(IV) and U(VI) removal by TODGA in ionic liquids: extraction behavior and mechanism, and radiation effect.Nuclear Science and Techniques, 2017, 28(5): 62     doi: 10.1007/s41365-017-0214-y
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Abstract:

Extraction behavior of thorium(IV) and uranium(VI) from nitric acid (HNO3) was studied using N,N,N',N'-tetraoctyldiglycolamide (TODGA) as extractant in different ionic liquids, and isooctane as comparison. Slope analyses with varying HNO3 concentrations and diluents revealed the extraction mechanism. With increasing length of alkyl chain and HNO3 concentration, the extraction mechanism of TODGA/IL system changed from cation exchange to neutral complex and/or anion exchange, and the molar ratio between TODGA and metal ions varied gradually from 2:1 to 1:1 for Th(IV) and 3:1 to 1:1 for U(VI). The kinetics and thermodynamic studies of Th(IV) and U(VI) by the best TODGA/[C2mim][NTf2] system showed that the extraction equilibrium was reached within 2 h and extraction reactions were endothermic. Compared to TODGA/isooctane system, TODGA/[C2mim][NTf2] system presented higher radiation stability under cirradiation. Therefore, it would have a promising application in spent fuel reprocessing.

Key words: Extraction, TODGA, Ionic liquids, Thorium(IV) and uranium(VI), Radiation effect