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The robotized chemical treatment of diluted spent fuel samples prior to isotope dilution analysis

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Abstract

A system made up by a Zymark robot and a separation automate preteats spent fuel samples and monitors a tri-n-octylphosphine oxide column extraction chromatographic procedure in order to isolate and purify uranium and plutonium present in the samples, prior to the spectrometric measurements. Up to 16 subsamples of spent fuel in dried or solution form are handled simultaneously in a completely unattended mode. The throughput of the robotized analytical procedure has increased by a factor of 3 compared to the earlier manual procedure without loss in the quality of the chemical treatment and of the mass- and α-spectrometric measurements.

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References

  1. J. CESARIO, P. LOHEZ, G. RETALI, Chaines complète d'Automates pour l'analyse par Spectrométrie de Masse des Solutions de Combustibles Irradiés, Colloque international sur l'application des garanties aux matières nucléaires, Vienne, 10–14 Nov., 1986.

  2. L. KOCH, et al., Isotopenpraxis 24 (1988) 229.

    Google Scholar 

  3. M. TAKAHASHI, Y. KATO, S. UCHIKOSHI, T. HATAKENAKA, K. YASU, S. NOMURA, Development of Automated Analytical System for Input Solution Sample by Isotope Dilution Method, Proc. 11th ESARDA Symp., Luxemburg, 30 May–1 June 1989, 1989, p. 529.

  4. A DELLE SITE et al., A New Procedure for the Extraction Chromatography Separation of Safeguards Samples with Tri-n-octylphosphine Oxide, IAEA/RL/119, IAEA, Vienna, May 1985.

    Google Scholar 

  5. R. J. SHARP et al., Anal. Chem., 60 (1988) No 18, 1056A.

    Google Scholar 

  6. M. B. DENTON, Analyst, 122 (Apr. 1987) 347.

    Google Scholar 

  7. S. DERON, Destructive Analysis: A Tool for Safeguards, in: IAEA Yearbook 1990, Vienna, 1990, p. E17.

  8. J. C. WHITE, W. J. ROSS, Separations by Solvent Extraction with Tri-n-octylphosphine Oxide, Technical Report, Oak Ridge National Laboratory, Oak Ridge. TN, Feb. 1961.

    Google Scholar 

  9. A. DELLE SITE et al., Reversed Phase Chromatographic Separations with Tri-n-octylphosphibe Oxide for the Isotopic and Isotope Dilution Analysis of Light Water Reactor Nuclear Fuel Materials, IAEA/RL/120, IAEA, Vienna, May 1985.

    Google Scholar 

  10. H. SWIETLY, Working Procedure for the Preparation of Spent Fuel Samples in Dried Nitrate Form, SAL/IR/2. IAEA, Vienna, 1987.

    Google Scholar 

  11. P. ZAHRADNIK, H. SWIETLY, N. DOUBEK, G. BAGLIANO, A. column exchange chromatographic procedure for the automated purification of analytical samples in nuclear spent fuel reprocessing and plutonium fuel fabrication, IAEA, Vienna, (in preparation).

  12. M. MIGUEL, A. DELLE SITE, S. DERON, H. SWIETLY, Nucl. Inst. Methods Phys. Res. 223 (1984) 270.

    Google Scholar 

  13. S. DERON, Determination of the Isotopic and Elemental Uranium and Plutonium Contents of Nitric Acid Solution by Mass Spectrometry, IAEA/RL/72, IAEA, Vienna, Nov. 1986.

    Google Scholar 

  14. K. MOTOJIMA, J. Nucl. Sci. Technol., Tokyo, 26 (1989) 358.

    Google Scholar 

  15. A. GOLDMAN, P. DERIDDER, G. LÁSZLÓ, Optimal Sample/Tracer Ratio for Isotope Dilution Mass Spectrometry, Interoffice Memorandum, IAEA, Vienna EDE-177/89, M7.32.

  16. G. LÁSZLÓ et al., Optimal Sample/Tracer Ratio for Isotope Dilution Mass Spectrometry: The Poly Isotope case, Proc. 13th ESARDA Symp., Avignon, 14–16 May 1991, 1991, p. 219.

  17. SAL/IAEA, Safety Analysis Report for the Input-Lab robot, SAL/IR/7, IAEA, Vienna, March. 1990.

    Google Scholar 

  18. ZYMARK Corp., Zymate System User's Manual, Hopkinton MA 01748, 1988.

  19. P. ZAHRADNIK, H. SWIETLY, Operation Instructions of the Input-Lab robot; Part III: The Software of the System, SAL/IR/8. IAEA, Vienna, 1992.

    Google Scholar 

  20. P. ZAHRADNIK, H. SUWIETLY, Operation Instructions of the Input-Lab robot; Part II, Chemical Preparation of Spent Fuel Samples before Isotope and Isotope Dilution Analysis, SAL/IR/7, IAEA, Vienna, 1992.

    Google Scholar 

  21. E. KUHN et al., International Target Values for Uncertainty Components in Fissile Isotope and Element Accountancy for Effective Safeguards of Nuclear Materials, IAEA Consultant's Group on International Standards of Measurements, IAEA, Vienna, June 1991.

    Google Scholar 

  22. N. DOUBEK et al., Preparation and Validation of a Large Size Dried Spike: Batch SAL-9951, IAEA/AL/040, IAEA, Vienna, Feb. 1991.

    Google Scholar 

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Authors and Affiliations

  1. Safeguards Analytical Laboratories, International Atomic Energy Agency, A-2244, Seibersdorf, (Austria)

    P. Zahradnik & H. Swietly

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  1. P. Zahradnik
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  2. H. Swietly
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Zahradnik, P., Swietly, H. The robotized chemical treatment of diluted spent fuel samples prior to isotope dilution analysis. Journal of Radioanalytical and Nuclear Chemistry, Articles 204, 145–157 (1996). https://doi.org/10.1007/BF02060875

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  • DOI: https://doi.org/10.1007/BF02060875

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