Abstract
A systematic study was undertaken of the chemical stability and structure of Cs-containing materials, prepared from Cs-saturated zeolite-containing rocks (ZCRs) by high temperature roasting, mainly in the absence of boron compounds.
Cs was introduced into the ZCRs via two procedures: (1) via an ion-exchange process between Cs in solution and the ZCRs; (2) by mixing ZCR powder with CsNO3 solution. Cs-containing ZCRs prepared by the two methods were heated at various temperatures up to 1400 °C. The chemical stability of the resulting glass-crystalline material was determined by measuring the amount of Cs passing into solution at various pH levels ranging from 1 to 12. The experiments lasted from 1 to 28 or more days.
It was found that heating ZCR at 1000 °C results in the strong immobilisation of Cs, Al, Na, K, Mg regardless of the way in which Cs was introduced into the ZCR. The lowest quantities of leached cations Cs, Al, Si, Na, K, Ca, Mg were detected in neutral solutions. The amount of Cs leaching into solution at pH=5 from products roasted at tempreatures >1000 °C was < 10−5 g cm−2 d-1 for the ZCR of all deposits studied. For the clay, the corresponding amount of Cs was about one order of magnitude higher. The crystal structure of the roasted material depends strongly on its Cs content: at a Cs content lower than 1 mgequiv g−1, the material comprised a predominantly amorphous phase; at higher Cs content, it was a mixture of amorphous and crystalline phases: ortho-rhombic (CsAISi5O12) and/or cubic — pollucite (CsAlSi2O6). The quantity of crystalline phases was greater when the second procedure for introducing Cs into the rocks was used.
Thus, from the results obtained here, ZCRs are shown to be a good candidate for radioactive waste conditioning and final disposal. Such a wasteform may be used not only in radionuclide decontamination processes, but also as a flux additive resulting in the formation of chemically- and mechanically-resistant Cs-containing glass-crystalline materials.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Preview
Unable to display preview. Download preview PDF.
References
Lin, K.H. (1991) An overview of radioactive waste management technology development, Current status and trends, J. Environ. Sci. Health, A26, (3), 373–393.
IAEA (1995) Handling of radioactive waste, IAEA Publication, Vienna, 42pp. (in Russian).
Nikiforov, A.S. (1990) Technical policy of radioactive wastes handling in the USSR, Teploenergetika, 1990 (8), 37–41 (in Russian).
Kedrovskii, O.L., Shishic, I.YU., Gupalo, T.A. et al. (1991) Establishment of isolation requirements for high-level radioactive wastes in geological formations, Atomnaya energiya, 70, (5), 294–297 (in Russian).
Kedrovskii, O.L., Rybalchenko, A.I., Pimenov, N.K. et al. (1991) Deep sited disposal of liquid radioactive wastes in porous geological formations, Atomnaya energiya 70TO, (5), 298–300 (in Russian).
Dublyansky, Yu, Lapin, B.N., Reutski, V. et al.(1996) Geological history of Yucca Mountain (Nevada) and the problem of the high-level nuclear waste repository, Abstracts of International Workshop Meeting Defence Nuclear Waste Disposal in Russia, 24–26 June, 1996, Krasnoyarsk, pp. 194–195.
Energiya (1992) U.S.A. Program on nuclear military plant waste removal Energiya: ekonomika-technika-ekologiya, 1992 (2), 47–49 (in Russian).
Belitsky, I.A., Bogdanova, V.I., and Fursenko, B.A. (1992) Ecological and chemical-technical problems of possible utilisation of zeolite-containing rocks for the recovery of territories subjected to radioactive pollution, in Prirodnye Zeolity Rossii, Abstracts of Republican Conference, November 25–27, 1991, Novosibirsk, 49–54 (in Russian).
Belitsky, I.A., Bogdanova, V.I., and Fursenko, B.A. (1992) Ecological and chemical-technical problems of possible utilisation of zeolite-containing rocks for the recovery of territories subjected to radioactive pollution, in Prirodnye Zeolity Rossii, Abstracts of Republican Conference, November 25–27, 1991, Novosibirsk, 49–54 (in Russian).
Stefanovsky, S.V. (1993) Immobilisation of sulphate-containing radioactive waste in glass, Physika i khimiya obrabotki materialov 1993 (2), 63–64 (in Russian).
Sobolev, I.A., Korenkov, I.L., Khomchik, L.M. et al. (1989) Environmental Protection During Radioactive Waste Treatment, Energoatomizdat, Moscow, 154 pp. (in Russian).
Dimitriev, S.A., Stefanovsky, S.V., Knyazev, I.A. et al. (1993) Plasma-chemical processing of radioactive waste, Physika i khimiya obrabotki materialov 1993 (4), 65–74 (in Russian).
Hatch, L.P. (1953) Ultimate disposal of radioactive wastes, Am. Scientist 41, 410.
Baer, V. (1989) Industrial processes of high-level waste solution vitrification, IAEA Bulletin 31(4), 47–51.
Zhu, G.L. and Chan, CH.Y. (1989) Radioactive waste treatment: international review (contemporary tendency and development), IAEA Bulletin 31(4), 5 - 14.
Zakharenko, V.N., Kulichenko, V.V., and Krylova, N.V. (1981) On the possibility and conditions of intermediate-level waste vitrification, in Issledovaniya v oblasti pererabotki obluchennogo topliva i obezvrezhivaniya radioactivnych otchodov, Prague, ChSK AE, Volume 2, pp. 96–103 (in Russian).
Stepanovsky, S.V., Sobolev, I.A., Lifanov, F.A. etal. (1988) Microstructure and chemical resistance of glass containing intermediate-level waste, Radiokhimiya 30, (6), 820–824 (in Russian).
Molnar, L., Lukavsky, J., Vancl, V. et al.(1989) Present state of nuclear reactor waste treatment in Czechoslovakia, in Management of Low and Intermediate Level Radioactive Waste, Vienna, Volume 1, pp. 87–95.
Laverov, N.P., Kancel, A.V., Lisicin, A.K. et al. (1991) Basic problems of radioecology in connection with radioactive waste disposal, Atomnaya energiya 71 (6), 523–534. (in Russian).
Babaev, M.K. and Ganbar, D.M. (1989) The prospects of utilisation of mordenite raw material for preparing glass-crystalline materials, Doklady AN Azerbaidzhan SSR 45, (10), 36–39 (in Russian).
Konukxin, V.P. and Komlev, V.N. (1995) Nuclear Technologies and the Eco-sphere, Apatity, 335p (in Russian).
Bogdanova, V.I., Belitsky, I.A., PR. Edeina, L.M. et al.(1993) Cation-exchange capacity determination of zeolite-containing rock by absorbed ammonium, Institute of Mineralogy and Petrography Instruction No. 24, Novosibirsk, 18 pp.
Bogdanova V.I. Belitsky, I.A., Predeina, L.M. et al.(1993) Cation-exchange capacity determination of zeolite-containing rock by the sum of exchanged cations removed, Institute of Mineralogy and Petrography Instruction No. 25, Novosibirsk, 16 pp.
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 1998 Springer Science+Business Media Dordrecht
About this chapter
Cite this chapter
Bogdanova, V.I. et al. (1998). Caesium Immobilization using Zeolite-Containing Rocks and High Temperature Treatment. In: Stenhouse, M.J., Kirko, V.I. (eds) Defence Nuclear Waste Disposal in Russia: International Perspective. NATO ASI Series, vol 18. Springer, Dordrecht. https://doi.org/10.1007/978-94-011-5112-2_6
Download citation
DOI: https://doi.org/10.1007/978-94-011-5112-2_6
Publisher Name: Springer, Dordrecht
Print ISBN: 978-94-010-6148-3
Online ISBN: 978-94-011-5112-2
eBook Packages: Springer Book Archive