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Ultradisperse Composite Vitrified Host Materials of Monazite–Iron (Pyro)phosphate Type for Conservation of Nuclear Waste Concentrates

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Radiochemistry Aims and scope

Abstract

A new type of a promising glassy-crystalline host material was prepared by ultradisperse synthesis in model experiments. The starting product is the nitric acid fraction of fission products (Cs, Sr, Ba), obtained radiochemically from irradiated nuclear fuel of a WWER-1000 reactor (1000-MWel water-cooled water-moderated energy reactor). Equivalent amounts of La(NO3)3, H3PO4, and Fe2O3 are added, and water is removed on heating. After complete removal of moisture, the residue is calcined at 600°С. The phosphated calcinate is dispersed in acetone to obtain slurry and, after removing acetone, converted to the glassy form at 950°С by self-igniting high-temperature synthesis. The whole process of preparing the composite is performed in one container crucible, which is then sealed. The major constituent of the host material is iron (pyro)phosphate glass (~55%); the finely grained crystalline phase, according to X-ray diffraction data, consists mainly of monazite of the composition La2(Sr,Ba)3(PO4)4. The monazite content is about 40%. Monazite forms with the glass via covalent bonding a composite exhibiting high corrosion resistance. The steady-state rate of Cs leaching form the monazite glass is 0.1 μg cm–2 day–1 (90°С, 100 days).

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Authors and Affiliations

  1. St. Petersburg State University, Universitetskaya nab. 7/9, St. Petersburg, 199034, Russia

    R. A. Kuznetsov, I. G. Kanterman, V. V. Eremin & V. G. Semenov

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  1. R. A. Kuznetsov
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  2. I. G. Kanterman
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  3. V. V. Eremin
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  4. V. G. Semenov
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Correspondence to R. A. Kuznetsov.

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Original Russian Text © R.A. Kuznetsov, I.G. Kanterman, V.V. Eremin, V.G. Semenov, 2018, published in Radiokhimiya, 2018, Vol. 60, No. 3, pp. 279–283.

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Kuznetsov, R.A., Kanterman, I.G., Eremin, V.V. et al. Ultradisperse Composite Vitrified Host Materials of Monazite–Iron (Pyro)phosphate Type for Conservation of Nuclear Waste Concentrates. Radiochemistry 60, 323–327 (2018). https://doi.org/10.1134/S1066362218030165

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  • DOI: https://doi.org/10.1134/S1066362218030165

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