Abstract
Synthesis and characterization of N,N′-di-p-tolylpyridine-2,6-dicarboxamide (DTPDA) was carried out and used for extraction of U(VI) and Th(IV) from nitric acid solutions. The processes of extraction were determined by the slope analysis and by analyzing a function that allows the simultaneous treatment of all the experimental points obtained in different conditions. The different factors affecting the extraction distribution ratio(D) of U(VI) and Th(IV) (extraction concentration, concentrations of nitric acid, salting-out agent NaNO3 concentration, equilibration time and temperature) were investigated. The results obtained indicated that the extraction species of U(VI) and Th(IV) are mainly extracted as UO2(NO3)2·1.5DTPDA and Th(NO3)4·1.5DTPDA. The related thermodynamic functions were calculated. Back-extraction of U(VI) and Th(IV) from organic phases was also studied.
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Drew MGB, Hill C, Hudson MJ, Iveson PB, Madic C, Youngs TGA Dalton trans. (2004) 244
Nakamura S, Takei S, Akiba K (2002) Anal Sci 18:319
Kondo K, Kamio E (2002) Desalination 144:249
Turanov AN, Karandashev VK, Yarkevich AN, Kharitonov AV, Safronova ZV (2002) Radiochemistry 44:559
Suioy Biswas KN, Hareendran DK, Singh JN, Sharam SB, Roy J Radioanal Nucl Chem. 283(2010) 665
Abdel-Khalek AA, Ali MM, Hussein AE, Abdel-Magied AF (2011) J Radioanal Nucl Chem 288:1
Sharma JN, Ruhela R, Harindaran KN, Mishra SL, Tangri SK, Suri AK (2008) J Radioanal Nucl Chem 278:173
Ma G, Freiser H, Muralidharan S (1997) Anal Chem 69:2835
Bhattacharjee B (2003) An overview of R&D in fuel cycle activities of AHWR, 14th Indian Nuclear Society Annual Conference (INSAC). 4
Thorium Fuel cycle: Potential Benefits and Challenges, International Atomic Energy Agency (IAEA) Technical Document. (2005)1450
Condamines N, Musikas C (1992) Solvent Extr Ion Exch 10:69
Preston J, Dupreez A (1995) Solvent Extr Ion Exch 13:391
Wang YS, Shen CH, Zhu JK, Bao BR (1990) J Radioanal Nucl Chem 212:101
Spjuth L, Liljenzin J, Hudson M, Drew M, Iveson P, Madic C (2000) Solvent Extr Ion Exch 18:1
Mowafy EA, Aly HF (2001) J Radioanal Nucl Chem 250:199
Mowafy EA, Sc M (1996) Thesis. Zagazig University, Egypt
Mowafy EA (1999) Thesis. Zagazig University, Egypt
Upadhyay MJ, Bhattacharya PK (1992) J Mol Catal 73:277
Upadhyay MJ, Trivedi BM, Bhattacharya PK (1992) J Mol Catal 73:287
Jacob M, Bhattacharya PK (1989) J Mol Catal 54:131
Berthon L, Cordier PY, Bonvous F, In ISEC[C]. Melbourne Australia (1996) 1339
Bond WD, Schulz WW, Burger LL, Navratil JD (1990) Science and technology of tributyl Phosphate, application of tributyl phosphate in nuclear fuel reprocessing. CRC Press Inc. Boca Ratton, Florida
Shii IY, Ahama IWT, Sakaguchi S (1996) J Org Chem 61:4520
Ma HL, Cai QX (1964) Atom Energ Sci Technol 6:48
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The authors acknowledge the National Natural Science Foundation of China (J1210001) and Fundamental Research Funds for the Central Universities (860487) for providing financial support.
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Hu, P., Qian, L., He, Y. et al. Solvent extraction of uranium(VI) and thorium(IV) by N,N′-di-p-tolylpyridine-2,6-dicarboxamide from nitric acid solution. J Radioanal Nucl Chem 297, 133–137 (2013). https://doi.org/10.1007/s10967-012-2352-3
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DOI: https://doi.org/10.1007/s10967-012-2352-3