Journal of Radioanalytical and Nuclear Chemistry

, Volume 295, Issue 2, pp 1113–1117 | Cite as

Studies on solubility of TBP in aqueous solutions of fuel reprocessing

  • P. Velavendan
  • S. Ganesh
  • N. K. Pandey
  • R. Geetha
  • M. K. Ahmed
  • U. Kamachi Mudali
  • R. Natarajan


In nuclear technology, tri-n-butyl phosphate (TBP) diluted with a hydrocarbon diluent such as n-dodecane or NPH is the most frequently used solvent in liquid–liquid extraction for fuel reprocessing. This extraction, known as the plutonium uranium refining by extraction, is still considered as the most dominant process for the extraction of uranium and plutonium from irradiated fuels. The solubility of pure TBP in water is about 0.4 g/L at 25 °C. This is enough to create trouble during evaporation of raffinate and product solutions. Solubility data for undiluted TBP and TBP (diluted in inert hydrocarbon diluent) in various concentrations of nitric acid is not adequate in the literature. The solubility data generated in the present study provide complete information on the solubility of TBP in various nitric acid concentrations (0–15.7 M) at room temperature. The effect of heavy metal ion concentration such as uranium and various fission products on the solubility of TBP in nitric acid is also presented. The results obtained from gas chromatographic technique were compared with spectrophotometric technique by converting the organic phosphate into inorganic phosphate. The generated data is of direct relevance to reprocessing applications.


Gas chromatography Flame ionization detector Solubility Raffinate PUREX process Tri-n-butyl phosphate and evaporation 


  1. 1.
    Ramanujam R (1998) IANCAS Bull 2:14Google Scholar
  2. 2.
    Schulz WW, Navratil JD (1984) Science and technology of tributyl phosphate, vol 1, Chapter 7. CRS Press Inc., Boca RatonGoogle Scholar
  3. 3.
    Nichols GC (1960) Technical Report DP-526, E.I. Du Pont de Nemours & Company, Savannah River Laboratory, Aiken, SCGoogle Scholar
  4. 4.
    Lee Hyder M (1996) Nucl Technol 16:327Google Scholar
  5. 5.
    Robinson RN, Gutowski DM, Yeniscavich W (2003) Report DNFSB/TECH-33, Defense Nuclear Facilities Safety Board, WashingtonGoogle Scholar
  6. 6.
    Maeguchi H, Hayashi K, Matsuoka S, Shimada K (1991) OECD Specialist meeting on safety and risk management in fuel cycle facilities, Tokyo, Japan, October, p 475Google Scholar
  7. 7.
    Long JT (1978) Engineering for nuclear fuel reprocessing. American Nuclear Society, La Grange, pp 273–326Google Scholar
  8. 8.
    Benedict M, Pigford TH, Levi HW (1981) Nuclear chemical engineering. McGraw Hill Book Company, New York, p 512Google Scholar
  9. 9.
    Leroy P (1967) Technical Report ORNL TR 4344, Oak Ridge National Laboratory, Tennessee (Original French Report CEA-R-3207)Google Scholar
  10. 10.
    Geetha R (1996) Indian chemical engineering congressGoogle Scholar
  11. 11.
    Kuno Y, Hina T, Masui J (1993) J Nucl Sci Technol 30:567CrossRefGoogle Scholar
  12. 12.
    Burger LL, Forsman RC (1951) Technical Report HW 20936, Hanford works, General Electric & Co, Richland, WashingtonGoogle Scholar
  13. 13.
    Becker R, Stieglitz L, Bautz H (1981) PWA Report 96-81, Kernforschungszentrum, Karlsruhe, Federal Republic of GermanyGoogle Scholar
  14. 14.
    Ochsenfeld W, Schon J, Smits D, Tullius E (1976) J Nucl Eng Sci 18:258Google Scholar
  15. 15.
    Shekhar K, Koganti SB (2000) Nucl Technol 129:279Google Scholar
  16. 16.
    Shekhar K, Koganti SB (1999) Indian J Chem Technol 6:90Google Scholar
  17. 17.
    Hyder ML (1994) Report WSRC-TR-94-059, Westing house Savannah River Company, Aiken, South Carolina Google Scholar
  18. 18.
    Davis W, Mrochek J, Hardy CJ (1966) J Inorg Nucl Chem 28:2001CrossRefGoogle Scholar
  19. 19.
    Davis W, Mrochek J, Judkins RR (1970) J Inorg Nucl Chem 32:1689CrossRefGoogle Scholar
  20. 20.
    Davis WJ, Kibbey AH (1970) Report ORNL-TM-3062, Oak Ridge National Laboratory, TennesseeGoogle Scholar
  21. 21.
    Wright A, Hartmann PP (2010) Sep Sci Technol 45:1753CrossRefGoogle Scholar
  22. 22.
    Velavendan P, Ahmed MK, Geetha R (2007) Proceedings of the nuclear and radiochemistry symposium (NUCAR 2007), Vadodara, p 207Google Scholar
  23. 23.
    Belousov EA (1975) J Phys Chem 49:1695Google Scholar
  24. 24.
    Ganesh S, Velavendan P, Pandey NK, Ahmed MK, Kamachi Mudali U, Natarajan R (2012) J Radioanal Nucl Chem 293:529Google Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2012

Authors and Affiliations

  • P. Velavendan
    • 1
  • S. Ganesh
    • 1
  • N. K. Pandey
    • 1
  • R. Geetha
    • 2
  • M. K. Ahmed
    • 2
  • U. Kamachi Mudali
    • 1
  • R. Natarajan
    • 1
  1. 1.Reprocessing Research and Development Division, Reprocessing GroupIndira Gandhi Centre for Atomic ResearchKalpakkamIndia
  2. 2.Nuclear Fuel ComplexHyderabadIndia

Personalised recommendations