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Solvent wash studies for the removal of di-butyl phosphate from spent solvent under simulated PUREX condition

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Abstract

Reprocessing of high plutonium content spent nuclear fuel from fast reactors results in the generation of lean organic solution containing considerably high amount of di-butyl phosphoric acid. Use of sodium carbonate as wash reagent has constraints in the view point of process operation. In this context, an alternative method for the wash of radiolytically degraded 1.1 M TBP/n-dodecane was proposed. Studies indicated that that the use of 1.5 M of hydrazine carbonate was effective for the treatment of solvent degraded up to 300 kGy and the product obtained were comparable to the fresh solvent.

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References

  1. McKay HAC, Miles JH, Swanson JL (1984) The Purex process. In: Schulz WW, Burger LL, Navratil JD (eds) Science and technology of tri butyl phosphate, vol 3. CRS Press, Boca Raton

    Google Scholar 

  2. Herbst RS, Baron P, Nilsson M (2011) Standard and advanced separation: PUREX processes for nuclear fuel reprocessing. Adv Sep Tech Nucl Fuel Reprocess Radioact Waste Treat 6:141–175

    Google Scholar 

  3. Pavia AP, Malik P (2004) Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes. J Radioanal Nucl Chem 261(2):485–496

    Article  Google Scholar 

  4. Tahraoui A, Morris JH (1995) Decomposition of solvent extraction media during nuclear reprocessing: literature review. Sep Sci Technol 30(13):2603

    Article  CAS  Google Scholar 

  5. Dzhivanova ZV, Belova EV, Tkhorzhnitskii GP (2015) Radiation resistance of hydrocarbon diluents of tri-butyl phosphate in a two-phase system and carbonate regeneration of the solvent. Radiochemistry 57:143–151

    Article  CAS  Google Scholar 

  6. Natarajan R (2015) Reprocessing of spent fast reactor nuclear fuels. In: Taylor R (ed) Woodhead Publishing Series in Energy, reprocessing and recycling of spent nuclear fuel, pp 213–243. https://doi.org/10.1016/B978-1-78242-212-9.00009-

  7. Satyabrata M, Mallika C, Pandey NK, Mudali UK, Natarajan R (2015) Effect of radiolysis in altering the physiochemical and metal retention properties of solvent-diluent-acid systems. Sep Sci Technol 50(11):1671–1676

    Article  Google Scholar 

  8. Satyabrata M, Joshi S, Mallika C, Pandey NK (2017) Physicochemical properties of PUREX solvent on hydrolytic and chemical treatment. J Radioanal Nucl Chem 314:2301–2308

    Article  Google Scholar 

  9. Amber W, Patricia PH (2010) Review of physical and chemical properties of tri butyl phosphate/diluent/nitric acid systems. Sep Sci Technol 45:1753–1762

    Article  Google Scholar 

  10. Laurence B, Marie-Christine C (2010) Radiolysis of solvents used in nuclear fuel reprocessing. In: Sengupta AK, Moyer BA (eds) Ion exchange & solvent extraction, a series of advances, vol 19, chapter 8. CRS Press, Boca Raton

    Google Scholar 

  11. Satyabrata M, Pandey NK (2019) Physiochemical properties of gamma-irradiated tri-iso-amyl phosphate-dodecane system: effect of aqueous phase acidity. Solvent Extr Ion Exch 37(6):446–460

    Article  Google Scholar 

  12. Ginisty C, Guillaume B (1990) Solvent distillation studies for a PUREX reprocessing. Sep Sci Technol 25:1941–1952

    Article  CAS  Google Scholar 

  13. Reif DJ (1988) Canyon solvent cleaning with activated alumina. Nucl Technol 83:190–196

    Article  CAS  Google Scholar 

  14. Mike C, Billy K, Whittaker D, Taylor R, Wilden A, Modolo G, Iván SG, Ana NGA, Montano HG (2021) Status on solvent clean- up & recycling. GENIORS—D3.4—Issued on 2021-05-28 by NNL

  15. Araujo BF, Matsuda HT, Kuada TA, Araujo JA (1992) Continuous removal of radiolytic products from TBP extraction systems. J Radioanal Nucl Chem Lett 166:75–84

    Article  CAS  Google Scholar 

  16. Drain F, Moulin JP, Hugelmann D, Lucas P (1996) Advanced solvent management in reprocessing, 5 years of industrial experience. ISEC, pp 789–794

  17. Sugai H (1992) Crud in solvent washing process for nuclear fuel reprocessing. J Nucl Sci Technol 29:445–453

    Article  CAS  Google Scholar 

  18. Burger LL (1955) The chemistry of tri-butyl phosphate. United States Atomic Energy Commission Report HW-40910, Hanford Works, Richland, Washington

  19. 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 

  20. Germain M, Pluot P (1980) Diluent washing of aqueous phase using centrifugal contactors. In: Proceedings of the international solvent extraction conference ISEC’80, Liege, Belgium, pp 80–218

  21. Sicilio F, Goodgame TH, Wilkins B Jr (1961) Purification of irradiated tributyl phosphate by distillation in kerosene-type diluent. Nucl Sci Eng 9(4):455–461. https://doi.org/10.13182/NSE61-A25909P

    Article  Google Scholar 

  22. Mailen JC, Tallent OK (1984) Improved PUREX solvent scrubbing methods, Oak Ridge National Laboratory, CONF-840802-10, Tennessee

  23. Vishnu AP, Rajeev R, Velavendan P, Pandey NK, Mudali UK (2016) Modeling and simulation of diluent recovery unit in PUREX solvent regeneration system. Prog Nucl Energy 2016(104):359–367

    Google Scholar 

  24. Schulz WW (1970) Macro reticular ion exchange resin clean-up of PUREX process TBP solvent (No. ARH-SA-58-RD; CONF-710417-2). Atlantic Richfield Hanford Co., Richland

  25. Schulz WW (1972) Macro reticular anion exchange resin clean-up of PUREX process TBP solvent (No. ARH-SA-129; CONF-720607-21). Atlantic Richfield Hanford Co., Richland

  26. Mailen JC (1988) Secondary Purex solvent cleanup: laboratory development. Nucl Technol 83:182–189

    Article  CAS  Google Scholar 

  27. Tallent OK, Mailen JC (1982) An alternative solvent cleanup method using a hydrazine oxalate wash reagent. Nucl Technol 59:51–62

    Article  CAS  Google Scholar 

  28. Goldacker H, Schieder H, Steingrunn F, Stieglitz L (1976) A newly developed solvent wash process in nuclear fuel reprocessing decreasing the waste volume. Kerntechnik 18(10):426–430

    CAS  Google Scholar 

  29. Imaizumi H, Ban Y, Sato M, Asakura T, Morita Y (2005) Washing properties of n-butyl amine oxalate in degraded solvent. JAERI, Tokai

    Google Scholar 

  30. Klopfenstein RK, Krekeler RH, Leist NR, Hicks CT (1960) Studies of the behavior of the TBP-kerosene Solvent in uranium refining: quality evaluation and treatment techniques for used solvent. Office of Technical Services, Washington

    Google Scholar 

  31. Tallent OK, Crouse DJ, Mailen JC (1982) Method for cleaning solution used in nuclear fuel reprocessing. United States Patent US 4358426

  32. Natarajan R, Baldev R (2015) Technology development of fast reactor fuel reprocessing in India. Curr Sci 108:30–38

    CAS  Google Scholar 

  33. Govindan P, Sukumar S, Vijayan KS, Santhosh KG, Ganesh S, Sharma PK, Dhamodharan K, Subba RR, V, Venkataraman R, Natarajan R, (2010) Recovery of plutonium from carbonate wash solutions. J Radioanal Nucl Chem 284:151–156. https://doi.org/10.1007/s10967-010-0456-1

    Article  CAS  Google Scholar 

  34. Venkatesan KA, Kumaresan R, Antony MP, Kumar T, Srinivasan TG, Vasudeva Rao PR (2012) Characterization of high active waste (155 GWd/Te) arising from fast reactor fuel reprocessing. Radiochim Acta 100(11):843–850

    Article  CAS  Google Scholar 

  35. Satyabrata M, Anil KS, Sridhar M, Mallika C, Pandey NK, Mudali UK (2018) Identification of diluent degradation products in radiolyzed PUREX solvent. Solvent Extr Ion Exch 36(2018):54–65

    Google Scholar 

  36. Satyabrata M, Vishnu AP, Sridhar M, Pandey NK, Sankaran K, Joseph M (2019) Characterization of gamma irradiated PUREX solvent—a systematic study. Sep Sci Technol 55:1485–1494

    Google Scholar 

  37. Swanson JL (1971) The destruction of nitrous acid and hydrazoic acid in purex systems, BNWL-B-121. Battelle Pacific Northwest Laboratories

  38. Hardy CJ, Scargill D (1959) Studies on mono- and di-n-butyl phosphoric acids—II—the solubility and distribution of mono- and di-n butyl phosphoric acids in aqueous-organic solvent systems. J Inorg Nucl Chem 11:128–143

    Article  CAS  Google Scholar 

  39. Pierce RA, Thompson MC, Ray RJ (2001) Solubility limits of HDBP in U-nitric acid solutions. Sep Sci Technol 36(5–6):767–783

    Article  CAS  Google Scholar 

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Authors and Affiliations

  1. Reprocessing Group, IGCAR, Kalpakkam, TN, 603102, India

    Satyabrata Mishra, P. Vishnu Anand, Chayan Patra, Pranay Kumar Sinha, Chandan Mukhopadhyay, Jammu Ravi, D. Sivakumar, N. Desigan, R. Rajeev, K. Dhamodharan, P. Velavendan, K. A. Venkatesan & K. Ananthasivan

  2. Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, TN, 603102, India

    Puspalata Rajesh

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  1. Satyabrata Mishra
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Mishra, S., Anand, P.V., Patra, C. et al. Solvent wash studies for the removal of di-butyl phosphate from spent solvent under simulated PUREX condition. J Radioanal Nucl Chem 332, 343–353 (2023). https://doi.org/10.1007/s10967-022-08729-9

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