Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass

Abstract

The underground disposal of waste arising from the nuclear industry needs constant evaluation in order to improve upon it through minimizing the volume and cost by reducing the amount of glass used without compromising the safety of any leakage from the radioactive waste form. The immobilization of the spent resin (NRW-40) in borosilicate glass was investigated to meet the acceptance criteria for disposal of nuclear waste. The organic mixed bed resin in granular form was used as a waste target. The analysis of surrogate resin doped with radioactive and non-radioactive cesium (Cs) and cobalt (Co) was carried out to investigate their thermal and chemical properties and their compatibility with an alkaline borosilicate glass. The thermal analysis indicates that the structural damage caused by 1 mSv gamma radiation to the radioactive resin has altered its properties in comparison with the non-radioactive resin, same amount of cesium (8.88 wt%) and cobalt (1.88 wt%) were used in both resins. The immobilization of residue shows that the excess sulfur in the residue caused phase crystallization in the final glass matrix. It was found that the volatilization of Cs-137 and Co-60 from the successful radioactive resin-glass matrix (HG-3-IER-500) were more than that in the non-radioactive resin-glass matrix (HG-3-IEX-500). The study demonstrates comprehensive experimental and analytical works and shows that it is possible to minimise the volume of the waste while keeping the required safety levels, however further research needs to be carried out in this area.

Share and Cite:

N. Hamodi, K. Papadopoulou, T. Lowe and T. Abram, "Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass," New Journal of Glass and Ceramics, Vol. 2 No. 3, 2012, pp. 111-120. doi: 10.4236/njgc.2012.23016.

Conflicts of Interest

The authors declare no conflicts of interest.

References

[1] S. D. Alexandratos, “Ion Exchange Resin: A Retrospective from Industrial and Engineering Chemistry Research,” Journal of Industrial and Engineering Chemistry Research, Vol. 48, No. 1, 2009, pp. 388-394.doi:10.1021/ie801242v
[2] International Atomic Energy Agency, “Power Reactor Information System,” Vienna, 2010, pp.12-22.
[3] International Atomic Energy Agency, “Application of Ion Exchange Processes for the Treatment of Radioactive Waste and Management of Spent Ion Exchangers,” Technical Reports Series, No. 408, 2002, pp. 2-10.
[4] M. Ojovan, G. Petrov and S. Dmitriev, “Incineration of Wet Ion Exchange Resin Mixed with Metal Fuel,” Proceedings of International Conference on Waste Management WM’99, Tucson, 28 February-4 March 1999, CDROM.
[5] R. S. Juang and T. S. Lee, “Oxidative Pyrolysis of Organic Ion Exchange Resins in the Presence of Metal Oxide Catalysts,” Journal of Hazardous Materials, Vol. 92, No. 3, 2002, pp.301-314.doi:10.1016/S0304-3894(02)00025-0
[6] N. Hamodi, “Immobilisation of Spent IEX in Borosilicate Glass,” Master of Science Thesis, the University of Manchester, Manchester, 2008.
[7] N. D. Hutson and C. L. Crawford, “Treatment of Spent Argentine Ion Exchange Resin Using Vitrification,” Results of FY01 Testing at Savannah River Technology Centre, Aiken, 2002.
[8] P. Antonetti, Y. Claire, H. Massit, P. Lessart, C. Pham Van Cang and A. Perichaud, “Pyrolysis of Cobalt and Cesium Doped Cationic Ion-Exchange Resin,” Journal of Analytical and Applied Pyrolysis, Vol. 55, No. 1, 2000, pp. 89-91. doi:10.1016/S0165-2370(99)00075-3
[9] C. A. Cicero-Herman, D. Erich, J. Harden, K. Poole and P. Workman, “Commercial Ion Exchange Resin Vitrification in Borosilicate Glass,” Westinghouse Savannah River Company, Aiken, 1998.
[10] A. C. Silva and S. R. Mello-Castanho, “Vitrified Galvanic Waste Chemical Stability,” Journal of the European Ceramic Society, Vol. 27, No. 2-3, 2007, pp. 565-570.doi:10.1016/j.jeurceramsoc.2006.04.110
[11] D. S. Kim and P. Hrma, “Foaming in Glass Melts Produced by Sodium Sulfate Decomposition under Isothermal Conditions,” Journal of the American Ceramic Society, Vol. 74, No. 3, 2005, pp. 551-555.doi:10.1111/j.1151-2916.1991.tb04058.x
[12] N. Hamodi and Y. Iqbal, “Immobilisation of Ion Exchange Resin Arising from Nuclear Power Plants: An Introduction,” Journal of Pakistani Material Society, Vol. 3, No. 1, 2009.
[13] R. Streatfield, “Examples of Cement Formulation Development Work on Organic Ion Exchange Resins,” British Nuclear Group, Presentation 15th Meeting of the Radioactive Waste Information Network (RWIN), 31 January 2006, University of Sheffield, Sheffield.
[14] R. Rodriguez-Trejo, P. Bosch and S. Bulbulian, “Combustion Treatment of Co+2 and Cs+ Exchanged Zeolites,” Journal of Nuclear Materials, Vol. 354, No. 1-3, 2006, pp. 110-122. doi:10.1016/j.jnucmat.2006.02.100
[15] A. Nezu, T. Morrishima and T. Watanabe, “Thermal Plasma Treatment of Waste Ion-Exchange Resins Doped with Metals,” Journal of Thin Solid Film, Vol. 435, No. 1-2, 2003, pp. 335-339.
[16] N. Hamodi and Y. Iqbal, “Glass Melting Techniques Used in Radioactive Waste Immobilisation,” Journal of Pakistani Material Society, Vol. 3, No. 2, 2009.
[17] C. M. Jantzen, D. F. Bickford, K. G. Brown, A. D. Cozzi, C. C. Herman, J. C. Marra, D. K. Peeler, J. B. Pickett, R. F. Schumacher, M. E. Smith, J. C. Whitehouse and J. R. Zamecnik, “Savannah River Site Waste Vitrification Projects Initiated throughout the United States: Disposal and Recycle Options,” Westinghouse Savannah River Company, Aiken, 2000.
[18] P. U. Singare, R. S. Lokhande and R. S. Madyal, “Thermal Degradation Studies of Some Strongly Acidic Cation Exchange Resins,” Open Journal of Physical Chemistry, Vol. 1, No. 2, 2011, pp. 45-54.doi:10.4236/ojpc.2011.12007
[19] N. Bothe, F. Doscher, J. Klein and H. Widdecke, “Thermal Stability of Sulphonated Styrene-Divinylbenzene Resins,” Journal of Polymer, Vol. 20, No. 7, 1979, pp. 850-854. doi:10.1016/0032-3861(79)90122-8
[20] M. A. Dubois, J. F. Dozol, C. Nicotra, J. Serose and C. Massiani, “Pyrolysis and Incineration of Cationic Ion Exchange Resins—Identification of Volatile Degradation Compounds,” Journal of Analytical Applications and Pyrolysis, Vol. 31, 1995, pp.129-1340.doi:10.1016/0165-2370(94)00817-K
[21] R. K. Mishra, K. V. Sudarsan, P. Sengupta and R. K. Vatsa, “Role of Sulfate in Structural Modifications of Sodium Barium Borosilicate Glass Developed for Nuclear Waste Immobilisation,” Journal of American Ceramic Society, Vol. 91, No.12, 2008, pp. 3903-3907.
[22] L. D. Pye, A. Montenero and I. Joseeph, “Properties of Glass-Form Melts,” Taylor & Francis Group Publication, London, 2005, pp. 399-401. doi:10.1201/9781420027310
[23] C. N. Cascaval, G. Mocanu and A. Carpov, “Characterisation of Some Acrylic Anion-Exchangers by Pyrolysis-Gas Chromatography,” Journal of Thermal Analysis, Vol. 28, No. 2, 1983, pp. 325-332.doi:10.1007/BF01983267
[24] N. E. Bibler, W. T. Boyce, T. L. Fellinger, S. L. Marra, R. J. O’Drisscoll and J. W. Ray, “Tc-99 and Cs-137 Volatility from the DWPF Production Melter during Vitrification of the First Macrobatch at the Savannah River Site,” Westinghouse Savannah River Company, Aiken, 2001, pp. 7-9.

Copyright © 2024 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.