Abstract
A combination of the density and Raman measurements for rapid in situ determination of uranium concentration and free acid molarity in uranyl nitrate solutions is proposed. Laboratory validation and field tests performed using a portable handheld density meter and a handheld Raman spectrometer demonstrated a feasibility of the approach in the range of uranium concentration from 50 to 426 g L−1, and free acid molarity ≤ 3 M. The combined standard uncertainties of the uranium and free acidity determination were found to be 2.4% and 5.7%, respectively. Potentials of the method in safeguards and process control applications are highlighted.
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Notes
As noted in Ref [28], “free acidity of a solution containing hydrolysable metal ions is defined as the acidity in excess of the stoichiometrically balanced salts or the acidity without taking into account that contributed by the hydrolisis of such ions”.
For the sake of simplicity, the plutonium part is not shown in Eq. (1).
This is a simplication. For instance, Ikeda-Ohno et al. [33] concluded that speciation of uranium in uranyl nitrate is rather complex and can vary with the change of nitrate concentration.
Note that the measurements were performed during a plant’s shutdown period, when various maintenance activities could affect properties of technological media. For this reason, the measured uranium and free acid concentartions may not be enitrely representive of the process.
References
Loden L, Gilligan K (2013) Current and proposed process monitoring at uranium conversion facilities. Oak Ridge National Laboratory, ORNL/TM-2013/253
Advances in Uranium Refining and Conversion (1987) IAEA-TECDOC-420. International Atomic Energy Agency, Vienna
Uranium Extraction Technology (1993) Technical Reports Series No. 359. International Atomic Energy Agency, Vienna
De Bièvre P, Peiser H (1997) Basic equations and uncertainties in isotope-dilution mass spectrometry for traceability to SI of values obtained by this primary method. Fresenius J Anal Chem 359:523–525
Vogl J, Pritzkow W (2010) Isotope dilution mass spectrometry: a primary method of measurement and its role for RM certification. MAPAN J Metrol Soc I 25(3):135–164
Gray W, Davies W (1964) A rapid and specific volumetric method for the precise determination of uranium. TRG Report 716(D), Bombay, India
Safeguards Techniques and Equipment: 2011 Edition (2011) International nuclear verification series no. 1 (Rev. 2). International Atomic Energy Agency, Vienna
Canada T, Carpenter B (1979) Measurement technology for safeguards and materials control. NBS Special Publication, Boulder
Sprinkle J, Baxman H, Langner D, Canada T, Sampson T (1980) The in-plant evaluation of a uranium NDA system. In: Canada T, Carpenter B (eds) Measurement technology for safeguards and materials control. NBS Special Publication, Boulder
Ottmar H, Eberle H (1991) The hybrid K-edge/K-XRF densitometer: principles-design-performance. Report KfK 4590, Kernforschugszenturm Karlsruhe, Germany
Mosley W, Thomson M, Reynolds L (1980) Evaluation of an LIII x-ray absorption-edge densitometer for assay of mixed uranium-plutonium solutions. In: Canada T, Carpenter B (eds) Measurement technology for safeguards and materials control. NBS Special Publication, Boulder
Brooks M, Russo P, Sprinkle J (1985) A compact L-edge densitometer for uranium concentration assay. Report LA-10306-MS, Los Alamos National Laboratory, USA
Erdmann N, Amador P, Arboré P, Eberle H, Lützenkirchen K, Ottmar H, Schorlé H, van Belle P, Lipcsei F, Schwalbach P, Gunnink R (2009) COMPUCEA: a high-performance analysis procedure for timely on-site uranium accountancy verification in LEU fuel fabrication plants. ESARDA Bull 43:30–39
Berlizov A, Schachinger A, Roetsch K, Erdmann N, Schorlé H, Vargas M, Zsigrai J, Kulko A, Keselica M, Cailou F, Unsal V, Walczak-Typke A (2016) Feedback from operational experience of on-site deployment of bias defect analysis with COMPUCEA. J Radioannal Nucl Chem 307(4):1901–1909
Kierzek J, Parus J (1975) Rapid method of uranium determination in solutions based on X-ray fluorescence and absorption. J Radioannal Nucl Chem 24:73–84
Camp D, Ruhter W (1980) Nondestructive, energy-dispersive, x-ray fluorescence analysis of product stream concentrations from reprocessed nuclear fuels. In: Canada T, Carpenter B (eds) Measurement technology for safeguards and materials control. NBS Special Publication, Boulder
Berdikov V, lxGrigor’ev O, Iokhin B (1982) X-ray fluorescence determination of uranium and neighbouring elements in solution. J Radioannal Nucl Chem 68:181–192
Martinelli P, Boutaine J, Gousseau G, Tanguy J, Tellechea C (1986) Determination of uranium and/or plutonium using X-ray fluorescence analysis excited by 192Ir sealed sources. Nucl Instrum Methods Phys Res A 242(3):569–573
Dubrovka S, Chursin S, Verkhoturova V (2017) X-ray fluorescence-based method for the quantitative determination of uranium in the aqueous solutions. J Phys Conf Ser 781:012015
Khorfan A, Wahoud A, Rafool W (2003) A quick method to determine uranium concentration by gamma spectroscopy: its application for extraction of uranium from wet phosphoric acid. J Radioannal Nucl Chem 257:313–316
Dewji S, Chapman J, Lee D, Rauch E, Hertel N (2012) Detector validation and source term analysis of uranyl nitrate to detect diversion at natural uranium conversion cacilities. In: Proceedings of 53rd INMM annual meeting, Orlando, USA
Prohaska C (1957) A flow colorimeter for measuring uranium concentrations in process streams. DP-229
Landry J (1960) In-line instrumentation gamma monitor, uranium colorimeter. Oak Ridge National Laboratory, ORNL-2978
Scott F, Dirks R (1960) Photometer for continuous determination of uranium in radioactive process streams. Anal Chem 32:268–272
Bhargava V, Chandrasekharan E, Iyer R, Rao V, Ramaniah M, Srinivasan (1970) In-line analytical methods for fuel reprocessing streams-Part I. Direct calorimetry for uranium and free acid. Bhanha Atomic Reserach Centre, B.A.R.C.-510, Bombay, India
Bostick D (1980) Acid-compensated multiwavelength determination of uranium in process streams. In: Canada T, Carpenter B (eds) Measurement technology for safeguards and materials control. NBS Special Publication, Boulder
Smith N, Cerefice G, Czerwinski K (2013) Fluorescence and absorbance spectroscopy of the uranyl ion in nitric acid for process monitoring applications. J Radioanal Nucl Chem 295:1553–1560
Srinivasan T, Vasudeva Rao R (2014) Free acidity measurement: a review. Talanta 118:162–171
Nair B, Shanmugavelu P, Sudhakar T, Suchintya S (2009) Determination of uranium concentration and free acid in uranyl nitrate solutions by two-end point pH titration. Explor Res At Miner 19:44–47
Botts J, Raridon R, Costanzo D (1978) Density, acidity, and conductivity measurements of uranyl nitrate/nitric acid solutions. Oak Ridge National Laboratory, ORNL/TM-6491
Berlizov A, Ho Mer Lin D, Nicholl A, Fanghänel Th, Mayer K (2016) Assessing hand-held Raman spectrometer FirstDefender RM for nuclear safeguards applications. J Radioannal Nucl Chem 307(1):285–295
Sakurai S, Tachimori S (1996) Density equation of aqueous solution containing plutonium (IV), uranium (VI) and nitric acid. J Nucl Sci Technol 33(2):187–189
Ikeda-Ohno A, Hennig C, Tsushima S, Scheinost A, Bernhard G, Yaita T (2009) Speciation and structural study of U(IV) and -(VI) in perchloric and nitric acid solutions. Inorg Chem 48(15):7201–7210
Certified Nuclear Reference Materia No. 106. Uranium dioxide (sintered pellets). Certification of Analysis (1984) Commission of the European Communities. Joint Research Centre, Geel Establishmenet (CBNM)
SpectraLine 1.6. User’s Manual (2017) Laboratory of spectrometry and radiometry. LSRM Ltd., Zelenograd
Advances in Uranium Refining and Conversion (1986) IAEA-TECDOC-420. International Atomic Energy Agency, Vienna
Zhao K, Penkin M, Norman C, Balsley S (2010) International target values 2010 for measurement uncertainties in safeguarding nuclear materials. STR-368, International Atomic Energy Agency, Vienna
Acknowledgements
The author would like to gratefully acknowledge Mr Andreas Schachinger and Ms Rosanna Jungreithmair from the Nuclear Material Laboratory of the IAEA’s Safeguards Analytical Services in Seibersdorf for the assistance in preparation and characterization of reference solutions used in this study.
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Berlizov, A. A method for prompt in situ uranium assay and free acidity determination in uranyl nitrate solutions by density and Raman measurements. J Radioanal Nucl Chem 320, 775–784 (2019). https://doi.org/10.1007/s10967-019-06503-y
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DOI: https://doi.org/10.1007/s10967-019-06503-y