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Extraction and Preconcentration of dissolved dibutyl phosphoric acid (HDBP) from aqueous uranyl nitrate solutions for gas chromatographic analysis

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Abstract

With a view to mitigate the complexities associated with aqueous solubility of Organophosphorous solvent, accurate estimation of dissolved organic in aqueous streams assumes great importance. Present method employs solvent extraction using 10 % (v/v) mixture of benzyl alcohol-benzene (BBA) for selective enrichment/extraction of dissolved Dibutyl phosphosphoric acid (HDBP), the target analyte, in presence of tributyl phosphate from nitric acid solutions containing bulk amount of uranyl ions. The extracted HDBP after methylation is subjected to gas chromatographic analysis using thermal conductivity detector. A calibration plot of HDBP estimation in the concentration range of 10–100 ppm, yields a precision with RSD of ±5 %.

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References

  1. Schulz WW, Navratil JD (eds) (1984) Science and technology of Tri-Butyl phosphate, vol 3. CRC Press, Boca Raton

    Google Scholar 

  2. Tripathi SC, Ramanujam A, Nadkarni MN, Bandyopadhyay C (1986) Thin-layer chromatographic separation and determination of dibutylphosphoric acid in a mixture of monobutylphosphoric acid and tributyl phosphate. Analyst 111(2):239–240

    Article  CAS  Google Scholar 

  3. Misra SK, Mahatele AK, Tripathi SC, Dakshinamoorthy A (2009) Studies on the simultaneous removal of dissolved DBP and TBP as well as uranyl ions from aqueous solutions by using Micellar-Enhanced ultrafiltration technique. Hydrometallurgy 96(1–2):47–51

    Article  CAS  Google Scholar 

  4. Tripathi SC, Bindu P, Ramanujam A (2001) Studies on the identification of harmful radiolytic products of 30 % TBP-n-dodecane-HNO3 by gas liquid chromatography. I. Formation of diluent degradation products and their role in Pu retention behavior. Sep Sci Technol 36(7):1463–1478

    Article  CAS  Google Scholar 

  5. Mincher BJ, Mezyk SP (2009) Radiation chemical effects on radiochemistry: a review of examples important to nuclear power. Radiochim Acta 97(9):519–534

    Article  CAS  Google Scholar 

  6. Mossini E, Macerata E, Giola M, Brambilla L, Castiglioni C, Mariani M (2015) Radiation-induced modifications on physico chemical properties of diluted nitric acid solutions within advanced spent nuclear fuel reprocessing. J Radioanal Nucl Chem 304(1):395–400

    Article  CAS  Google Scholar 

  7. Tripathi SC, Kedari CS, Parikh KJ, Mishra SK, and Ramanujam A (1991) Esterification and determination of dibutyl phosphoric acid in presence of uranium by GLC in tributyl phosphate samples. In: Proceedings of international conference on chromatography, Aligarh Muslim University, UP, INDIA, Paper 28, pp 32

  8. Davis Jr W, Navratil JD, Laszttty A, Horva’th Z, (1984) Science and technology of Tri-Butyl phosphate. In: Schulz WW, JD Navratil (Eds) CRC Press, Boca Raton, Chapt 8

  9. Tripathi SC, Sumathi S, Ramanujam A (1999) Effects of solvent recycling on radiolytic degradation of 30 % tributyl phosphate-n-dodecane-HNO3 system. Sep Sci Technol 34(14):2887–2903

    Article  CAS  Google Scholar 

  10. Ritcey GM (1980) Crud in solvent extraction processing: a review of causes and treatment. Hydrometallurgy 5(2–3):97–107

    Article  CAS  Google Scholar 

  11. Chen J (2004) Crud in the solvent extraction process for spent fuel reprocessing. Yuanzineng Kexue Jishu/Atomic Energy Sci Technol 38(4):343–349

    CAS  Google Scholar 

  12. Sreenivasa Rao K, Shyamlal R, Narayan CV, Jambunathan U, Ramanujam A, Kansra VP (2003) Uranous nitrate production for Purex process applications using PtO2 catalyst and hydrazine nitrate as reductant, BARC/2003/E/009

  13. Nogami M, Hirose Y, Arai T et al (2008) Reduction of U (VI) and some fission products in HNO3 media by galvanostatic electrolysis. J Alloy Compd 451:358–360

    Article  CAS  Google Scholar 

  14. Fell SA (1989) Electrochemical generation of stable uranium (IV) fluoride sulfate solutions. Analyst 114:325–331

    Article  CAS  Google Scholar 

  15. Nichols GS (1966) Electrolytic preparation of uranous nitrate. DP-1065

  16. Parkinson N (1968) Electrolytic reduction of uranyl solutions. UP 3361651

  17. Dodi A, Verda G (2001) Improved determination of tributyl phosphate degradation products (mono-and dibutyl phosphates) by ion chromatography. J Chromatogr A 920(1–2):275–281

    Article  CAS  Google Scholar 

  18. Schulz WW, Navratil JD (eds) (1984) Science and technology of Tri-Butyl phosphate, vol 1. CRC Press, Boca Raton

    Google Scholar 

  19. Grant KE (1997) Determination of monobutyl phosphate and dibutyl phosphate in mixed hazardous wastes by Ion-Pair chromatography. J Radioanal Nucl Chem 220:31–35

    Article  CAS  Google Scholar 

  20. Lamouroux C, Virelizier H, Moulin C, Tabet JC, Jankowski CK (2000) Direct determination of dibutyl and monobutyl phosphate in a tributyl phosphate/nitric aqueous-phase system by electrospray mass spectrometry. Anal Chem 72(6):1186–1191

    Article  CAS  Google Scholar 

  21. Grant KE, Mong GM, Clauss SA, Wahl KL, Campbell JA (1997) Determination of monobutyl phosphate and dibutyl phosphate in mixed hazardous wastes by ion-pair chromatography. J Radioanal Nucl Chem 220(1):31–35

    Article  CAS  Google Scholar 

  22. Baldwin WH, Higgins CE (1961) Complexes of dibutyl phosphoric acid. J Inorg Nuclear Chem 17(3–4):334–336

    Article  CAS  Google Scholar 

  23. Krutikov PG, Solovkin AS (1970) Di-n-butyl phosphato compounds of uranyl. Russ J Inorg Chem 15:825–827

    Google Scholar 

  24. Mikhailov VA, Grigor’eva EF (1964) Salts of dialkyl hydrogen phosphates. Russ J Inorg Chem 9:477–481

    Google Scholar 

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Acknowledgments

Authors acknowledge their sincere thanks to Shri P. M. Gandhi, Head, Fuel Reprocessing Division, for his constant encouragement for the present investigation.

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Authors and Affiliations

  1. Fuel Reprocessing Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India

    S. C. Tripathi, M. Bindu & K. S. Rao

Authors
  1. S. C. Tripathi
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  2. M. Bindu
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  3. K. S. Rao
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Correspondence to S. C. Tripathi.

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Tripathi, S.C., Bindu, M. & Rao, K.S. Extraction and Preconcentration of dissolved dibutyl phosphoric acid (HDBP) from aqueous uranyl nitrate solutions for gas chromatographic analysis. J Radioanal Nucl Chem 308, 609–615 (2016). https://doi.org/10.1007/s10967-015-4413-x

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  • DOI: https://doi.org/10.1007/s10967-015-4413-x

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