Skip to main content
SpringerLink
Log in

Characteristics of vitrified liquid radioactive wastes prepared with the use of aqueous silica sols

  • Published:
Glass Physics and Chemistry Aims and scope Submit manuscript

Abstract

Solid samples of vitrified model liquid radioactive wastes (LRWs) are produced by treating their components with hydrochloric acid-water-alcohol solutions containing ethoxysilane hydrolysates and aqueous silica sols at pH 1.5–4.0. The silica sols are prepared by the membrane concentration of natural hydrothermal solutions. The characteristics of solid vitrified samples are determined using X-ray powder diffraction, thermogravimetry, IR spectroscopy, and electron microscopy. It is established that, in the acidic water-alcohol medium, ethoxysilane hydrolysates, silica sol nanoparticles, and dissolved salts of liquid radioactive wastes form a spatially structured inorganic siloxane copolymer.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. Pope, J.M., Harrison, D.E., and Lahoda, E.J., Cinder Aggregate from Purex Waste, US Patent 4487711, 1984.

  2. Pope, J.M. and Lahoda, E.J., Alcohol-Free Alkoxide Process for Containing Nuclear Waste, US Patent 4430257, 1984.

  3. Pope, J.M., Wood, S., and Harrison, D.E., Containing Nuclear Waste via Chemical Polymerization, US Patent 4377507, 1983.

  4. Aubert, B., Process for the Immobilization of Nuclear Waste in a Borosilicate Glass, US Patent 4772431, 1988.

  5. Aubert, B., Process for the Preparation of a Borosilicate Glass Containing Nuclear Waste, US Patent 4797232, 1989.

  6. Simmons, C.J., Simmons, J.H., Macedo, P.B., and Litovitz, Th.A., Fixation by Ion Exchange of Toxic Materials in a Glass Matrix, US Patent 4469628, 1984.

  7. Funabashi, K., Kawamura, F., Kikuchi, M., and Yusa, H., Process for Solidifying Radioactive Waste Pellets, US Patent 4505851, 1985.

  8. Wakabayashi, H., Terai, R., Yamanaka, H., and Hara, S., Process for Vitrifying Liquid Radioactive Waste, US Patent 4514329, 1985.

  9. Chickering, R.W., Yoldas, B.E., and Neuman, B.H., Nuclear Waste Encapsulation in Borosilicate Glass by Chemical Polymerization, US Patent 4 422 965, 1983.

  10. Yoldas, B., Monolithic Glass Formation, J. Mater. Sci., 1977, vol. 12, pp. 1203–1208.

    Article  ADS  CAS  Google Scholar 

  11. Yoldas, B., New Process Breaks Old Glass Theory, New Scientist, 1980, June, p. 396.

  12. Cadoff, L.H. and Smith-Magowan, D.B., Glass Former Composition and Method for Immobilizing of Nuclear Waste Using the Same, US Patent 4759879, 1988.

  13. Iler, R., Chemistry of Silica, New York, Wiley, 1979. Translated under the title Khimiya kremnezema, Moscow: Mir, 1982, parts 1–2.

    Google Scholar 

  14. Potapov, V.V., Gorbach, V.A., and Serdan, A.A., A Technique for Extracting Colloidal Silica from a Hydrothermal Heat Carrier with the Preparation of Silica-Containing Material with a Low Impurity Content, RF Patent 2296103, 2005.

  15. Potapov, V.V., Gorbach, V.A., Kashpura, V.N., and Antipin, L.M., A Technique for Using a Hydrothermal Heat Carrier, RF Patent 2309191, 2005.

  16. Potapov, V.V., Zelenkov, V.N., Gorbach, V.A., Kashpura, V.N., and Min, G.M., Izvlechenie kolloidnogo kremnezema iz gidrotermal’nykh rastvorov membrannymi metodami (Extraction of Colloidal Silica from Hydrothermal Solutions by Membrane Methods), Moscow: RAEN, 2005 [in Russian].

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Geotechnological Research Center, Far East Division, Russian Academy of Sciences, Severo-Vostochnoe sh. 30, Petropavlovsk-Kamchatskii, 683002, Russia

    V. V. Potapov, A. O. Sadovnikova & E. V. Shunina

  2. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninskii pr. 31, Moscow, 119991, Russia

    D. G. Kuznetsov & L. M. Antipin

Authors
  1. V. V. Potapov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. D. G. Kuznetsov
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. L. M. Antipin
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. A. O. Sadovnikova
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. E. V. Shunina
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to V. V. Potapov.

Additional information

Original Russian Text © V.V. Potapov, D.G. Kuznetsov, L.M. Antipin, A.O. Sadovnikova, E.V. Shunina, 2009, published in Fizika i Khimiya Stekla.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Potapov, V.V., Kuznetsov, D.G., Antipin, L.M. et al. Characteristics of vitrified liquid radioactive wastes prepared with the use of aqueous silica sols. Glass Phys Chem 35, 397–405 (2009). https://doi.org/10.1134/S1087659609040087

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S1087659609040087

Keywords

Search

Navigation