Removal of Ru from Simulated High-Level Waste Prior to the Final Vitrification into Borosilicate Glass Using Tin as the Alloying Element: Feasibility Study
Publication: Journal of Hazardous, Toxic, and Radioactive Waste
Volume 22, Issue 4
Abstract
Ruthenium (Ru) was removed from molten borosilicate glass containing simulated radioactive waste by using tin as the solvent metal. The metal and glass phases were separated from each other and examined by X-ray diffraction (XRD), scanning electron microscopy–energy dispersive X-ray spectroscopy (SEM-EDX). The composition of alloy and glass phases was analyzed by inductively coupled plasma optical emission spectroscopy (ICP-OES) and atomic absorption spectroscopy (AAS). The percent extraction fraction of Ru was found to be ~90%. Significant quantities of Fe, Te, Ni, and Mo were also found in the alloy phase. Formation of the intermetallic compound was observed in the Sn-Ru alloy. The recovery of Ru was ~90%. Some amounts of Ni, Fe, Te, and Mo were found to migrate to the metal phase, leaving Cs, Sr, and Zr in the glass phase.
Get full access to this article
View all available purchase options and get full access to this article.
Acknowledgments
The authors are grateful to Dr. U. Kamachi Mudali, Director, Materials Chemistry and Metal Fuel Cycle Group (MC & MFCG); Dr. M. Joseph, Associate Director, MC & FCG; Dr. C. Remash, Head, Materials Processing Chemistry Section/Pyrochemical and Materials Processing Division (PMPD); and Dr. V. Jayaraman, Head, Materials Chemistry Division for their encouragement and support. The analytical chemistry section of Materials Chemistry Division/MC & MFCG, Indira Gandhi Centre for Atomic Research is duly acknowledged for analyzing the samples for determining the elemental composition of the metal buttons. The authors acknowledge Mr. Swapan Kumar Mahato for examining the metal and glass samples by SEM-EDX.
References
Advocat, T., P. Jollivet, J. L. Crovisier, and M. del Nero. 2001. “Long term alteration mechanisms in water for SON68 radioactive borosilicate glass.” J. Nucl. Mater. 298 (1–2): 55–62. https://doi.org/10.1016/S0022-3115(01)00621-3.
Barin, I., and O. Knacke. 1973. Thermochemical properties of inorganic substances. Berlin, Germany: Springer.
Blicharska, M., B. Bartoś, S. Krajewski, and A. Bilewicz. 2013. “Separation of fission produced 106Ru from simulated high level nuclear wastes for production of brachytherapy sources.” J. Radioanal. Nucl. Chem. 298 (3): 1713–1716. https://doi.org/10.1007/s10967-013-2570-3.
Chapman, C. C., J. M. Pope, and S. M. Barnes. 1986. “Electric melting of nuclear waste glasses: State of the art.” J. Non-Cryst. Solids 84 (1–3): 226–240. https://doi.org/10.1016/0022-3093(86)90781-7.
Chase, M. W., C. A. Davies, J. R. Downey, Jr., D. J. Fruip, R. A. McDonald, and A. N. Syverud. 1985. “JANAF thermochemical tables, 3rd edition, parts I and II.” Supplement, J. Phys. Chem. Ref. Data. 14(S1): 1–1896.
Ellingham, H. J. T. 1944. “Reducibility of oxides and sulphides in metallurgical processes.” J. Soc. Chem. Ind. 63: 125. https://doi.org/10.1002/jctb.5000630501.
Igarashi, H., and T. Takahashi. 1991. “The draining of noble metals in vitrified nuclear waste by a melter with a sloping floor.” Glass Technol. 32 (2): 46–50.
Jena, H., K. V. G. Kutty, and P. R. V. Rao. 2011. “Effect of temperature on the extraction of Pd by liquid tin from molten borosilicate glass containing simulated radwaste.” J. Non-Cryst. Solids 357 (15): 2911–2919. https://doi.org/10.1016/j.jnoncrysol.2011.03.033.
Jena, H., R. R. Madhavan, K. V. G. Kutty, and P. R. V. Rao. 2015. “Feasibility studies on Pd removal from molten BSG containing simulated nuclear waste using lead or aluminum as a solvent metal.” J. Hazard. Toxic Radioact. Waste 19 (2): 2153–2161. https://doi.org/10.1061/(ASCE)HZ.2153-5515.0000228.
Jensen, G. A., A. M. Platt, G. B. Mellinger, and W. J. Bjorklund. 1984. “Recovery of noble metals from fission products.” Nucl. Technol. 65 (2): 305–324. https://doi.org/10.13182/NT84-A33413.
Luckscheiter, B., and M. Nesovic. 1996. “Development of glasses for the vitrification of high level liquid waste (HLLW) in a Joule heated ceramic melter.” Waste Manag. 16 (7): 571–578. https://doi.org/10.1016/S0956-053X(97)88231-1.
Lutze, W., and R. C. Ewing, eds. 1988. Radioactive waste forms for the future. Amsterdam, Netherlands: North-Holland.
Naito, K., T. Matsui, and Y. Tanaka. 1986. “Recovery of noble-metals from insoluble residue of spent fuel.” J. Nucl. Sci. Technol. 23 (6): 540–549. https://doi.org/10.1080/18811248.1986.9735017.
Pflieger, R., M. Malki, Y. Guari, J. Larionova, and A. Grandjean. 2009. “Electrical conductivity of RuO2-borosilicate glasses: Effect of the synthesis route.” J. Am. Ceram. Soc. 92 (7): 1560–1566. https://doi.org/10.1111/j.1551-2916.2009.03088.x.
Rindone, G. E., and J. L. Rhoads. 1956. “The colors of platinum, palladium and rhodium in simple glasses.” J. Am. Ceram. Soc. 39 (5): 173–180. https://doi.org/10.1111/j.1151-2916.1956.tb15640.x.
Ronneau, C., J. Cara, and A. Rimski-Korsakov. 1995. “Oxidation-enhanced emission of ruthenium from nuclear fuel.” J. Environ. Radioactiv. 26 (1): 63–70. https://doi.org/10.1016/0265-931X(95)91633-F.
Schreiber, H. D. 1986. “Redox processes in glass forming melts.” J. Non-Cryst. Solids 84 (1–3): 129–141. https://doi.org/10.1016/0022-3093(86)90770-2.
Schreiber, H. D., T. R. Harville, and G. N. Damron. 1990. “Redox-controlled solubility of palladium in a borosilicate glass melt.” J. Am. Ceram. Soc. 73 (5): 1435–1437. https://doi.org/10.1111/j.1151-2916.1990.tb05220.x.
Schreiber, H. D., and A. L. Hockman. 1987. “Redox chemistry in candidate glasses for nuclear waste immobilization.” J. Am. Ceram. Soc. 70 (8): 591–594. https://doi.org/10.1111/j.1151-2916.1987.tb05712.x.
Schreiber, H. D., F. A. Settle, P. L. Jamison, J. P. Eckenrode, and G. W. Headley. 1986. “Ruthenium in glass forming borosilicate melts.” J. Less-Common Met. 115 (1): 145–154. https://doi.org/10.1016/0022-5088(86)90379-6.
Swain, P., C. Mallika, K. Sankaran, N. K. Pandey,U. Kamachi Mudali, and R. Natarajan. 2014. “Feasibility studies on the separation of ruthenium from high level liquid waste by constant potential electro-oxidation.” Prog. Nucl. Energy 75: 198–206. https://doi.org/10.1016/j.pnucene.2014.04.017.
Tooley, F. V. 1984. Vols. 1–2 of The handbook of glass manufacture: A book of reference for the plant executive and engineer. 3rd ed. New York, NY: Ashlee Publishing Company.
Uruga, K., K. Sawada, Y. Arita, Y. Enokida, and I. Yamamoto. 2007. “Removal of platinum group metals contained in molten glass using copper.” J. Nucl. Sci. Technol. 44 (7): 1024–1031. https://doi.org/10.1080/18811248.2007.9711342.
Uruga, K., K. Sawada, Y. Enokida, and Y. Yamamoto. 2008. “Liquid metal extraction for removal of molybdenum from molten glass containing simulated nuclear waste elements.” J. Nucl. Sci. Techol. 45 (10): 1063–1071. https://doi.org/10.1080/18811248.2008.9711893.
Information & Authors
Information
Published In
Journal of Hazardous, Toxic, and Radioactive Waste
Volume 22 • Issue 4 • October 2018
Copyright
©2018 American Society of Civil Engineers.
History
Received: Sep 25, 2017
Accepted: Feb 7, 2018
Published online: Jun 20, 2018
Published in print: Oct 1, 2018
Discussion open until: Nov 20, 2018
Authors
Metrics & Citations
Metrics
Citations
Download citation
If you have the appropriate software installed, you can download article citation data to the citation manager of your choice. Simply select your manager software from the list below and click Download.