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Recovery of americium from analytical solid waste containing large amounts of uranium, plutonium and silver

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Abstract

Trace metallic impurity analysis by spectroscopic techniques is one of the important steps of chemical quality control of nuclear fuel materials. Depending on the burn-up and the storage time of the fuel, there is an accumulation of 241Am in plutonium based fuel materials due to β decay of 241Pu. In this paper, attempts were made to develop a method for separation of 241Am from 1.2 kg of analytical solid waste containing 70% U, 23% Pu, 5% Ag and 1–2% C as major constituents along with other minor constituents generated during trace metal assay of plutonium based fuel samples by d. c. arc carrier distillation atomic emission spectrometry. A combination of ion exchange, solvent extraction and precipitation methods were carried out to separate ~45 mg of 241Am as Am(NO3)3 from 15 L of the analytical waste solution. Dowex 1×4 ion exchange chromatographic method was used for separation of Pu whereas 30% TBP–kerosene was utilized for separation of U. Am was separated from other impurities by fluoride precipitation followed by conversion to nitrate. The recovery of Pu from ion exchange chromatographic separation step was ~93% while the cumulative recovery of Am after separation process was found to be ~90%.

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References

  1. Gopalkrishnan M, Radhakrishnan K, Dhami PS, Kulkarni VT, Joshi MV, Patwardhan AB, Ramanujam A, Mathur JN (1997) Determination of trace impurities in uranium, thorium and plutonium matrices by solvent extraction and inductively coupled plasma atomic emission spectrometry. Talanta 44(2):169–176

    Article  CAS  Google Scholar 

  2. Satyanarayana K, Durani S (2010) Separation and inductively coupled plasma optical emission spectrometric (ICP-OES) determination of trace impurities in nuclear grade uranium oxide. J Radioanal Nucl Chem 285(3):659–665

    Article  CAS  Google Scholar 

  3. Rajeswari B, Dhawale BA, Bangia TR, Mathur JN, Page AG (2002) Role of Cyanex-272 as an extractant for uranium in the determination of rare earths by ICP-AES. J Radioanal Nucl Chem 254(3):479–483

    Article  CAS  Google Scholar 

  4. Argekar AA, Kulkarni MJ, Mathur JN, Page AG (2002) Chemical separation and ICP-AES determination of 22 metallic elements in U and Pu matrices using cyanex-923 extractant and studies on stripping of U and Pu. Talanta 56(4):591–601

    Article  CAS  Google Scholar 

  5. Chandramouleeswaran S, Upadya JC (2009) Trace element analysis of uranium samples: Routine analysis methodology. Exploration Res Atomic Miner 19:54–56

    CAS  Google Scholar 

  6. Sengupta A, Kulkarni MJ, Godbole SV (2011) Analytical application of DHOAfor the determination of trace metallic constituents in U based fuel materials by ICP-AES. J Radioanal Nucl Chem. doi:10.1007/s10967-011-1222-8

  7. Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade plutonium dioxide powders and pellets. ASTM C-697–10

  8. Carter JA, Sites JR (1970) Analytical chemistry division annual progress report. In: Raaen HP (ed) USAEC Report ORNL-4466, AERDB, Oak Ridge pp 93–94

  9. Johnson AJ, Kozy A, Morris RN (1969) Sodium fluoride as a spectrographic carrier for plutonium metal analysis. USAEC Report RFP-143, AERDB, Golden

  10. Page AG, Dalvi AGI, Godbole SV, Babu Y, Seshagiri TK, Sastry MD (1986) Trace metal assay of fast breeder test reactor fuel using d.c.arc and plasma emission. BARC-1334

  11. Page AG, Godbole SV, Deshkar S, Babu Y, Joshi BD (1977) Spectographic determination of trace metallic elements in uranium using a mixed carrier: Ga2O3 and SrF2. Fresenius J Anal Chem 287:304

    Article  CAS  Google Scholar 

  12. Sengupta A, Adya VC, Mohapatra PK, Godbole SV, Manchanda VK (2010) Separation and purification of americium from analytical waste solutions. J Radioanal Nucl Chem 283:777–783

    Article  CAS  Google Scholar 

  13. Michel H, Barci-Funel G, Dalmasso J, Ardisson G (1999) One step ion exchange process for the radiochemical separation of americium, plutonium and neptunium in sediments. J Radioanal Nucl Chem 240:467–470

    Article  CAS  Google Scholar 

  14. Ruikar PB, Nagar MS, Subramanian MS, Gupta KK, Varadarajan N, Singh RK (1995) Extraction behavior of uranium, plutonium and some fission products with gamma pre irradiated n-dodecane solutions of N,N′-dihexyl substituted amides. J Radioanal Nucl Chem 196:171–178

    Article  CAS  Google Scholar 

  15. Usuda S (1988) Rapid ion exchange separation of actinides. J Radioanal Nucl Chem 123:619–631

    Article  CAS  Google Scholar 

  16. Horwitz EP, Dietz ML, Chirizia R (1992) The application of novel extraction chromatographic materials to the characterization of radioactive waste solutions. J Radioanal Nucl Chem 161:575–583

    Article  CAS  Google Scholar 

  17. Thakkar AH (2001) Rapid sequential separation of actinides using eichrome’s extraction chromatographic materials. J Radioanal Nucl Chem 248:453–456

    Article  CAS  Google Scholar 

  18. Choppin GR, Dinus RH (1961) Ion-exchange studies of the lanthanides and actinides in concentrated mineral acids. Inorganic chem 1:140–145

    Article  Google Scholar 

  19. Morita Y, Sasaki Y, Asakura T, Kitatsuji Y, Sugo Y, Kimura T (2010) Development of a new extractant and new extraction process for minor actinide separation. IOP conference series. Mater Sci Eng 9:012057. doi:10.1088/1757-899X/9/1/012057

    Google Scholar 

  20. Proctor SG (1976) A new process for americium purification. J Less-Common Metals 44:195–199

    Article  CAS  Google Scholar 

  21. Ryan VA, Prigle JW (1960) Preparation of pure americium, RFP–130, UC-4, Chemistry general, TID–4500, 15th edn. U.S. Atomic energy agency commission contract AT (29-1)-1106

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Authors and Affiliations

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

    V. C. Adya, A. Sengupta, B. A. Dhawale, B. Rajeswari, S. K. Thulasidas & S. V. Godbole

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  1. V. C. Adya
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  2. A. Sengupta
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  3. B. A. Dhawale
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  4. B. Rajeswari
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  5. S. K. Thulasidas
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  6. S. V. Godbole
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Correspondence to S. V. Godbole.

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Adya, V.C., Sengupta, A., Dhawale, B.A. et al. Recovery of americium from analytical solid waste containing large amounts of uranium, plutonium and silver. J Radioanal Nucl Chem 291, 843–848 (2012). https://doi.org/10.1007/s10967-011-1360-z

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