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Thermal Stability of Glass with Simulators of Chloride Highly Radioactive Wastes

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Abstract

High temperature behavior of sodium–aluminum fluorophosphate glass—a potential matrix for immobilisation of waste salt electrolyte from pyrochemical reprocessing of irradiated nuclear fuel (INF) has been studied. The glass crystallizes between 430 and 640°C with formation of phosphate phases, which dissolve above 640°C leading to homogenization of the glass. Similar transformations of the glass matrix due to heating from the decay of short-lived fission products may have a negative effect on properties of vitrified radioactive chloride wastes during storage in a repository.

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Authors and Affiliations

  1. Institute of Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry, Russian Academy of Sciences, 109017, Moscow, Russia

    S. V. Yudintsev & A. A. Shiryaev

  2. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, 119071, Moscow, Russia

    S. V. Yudintsev & A. A. Shiryaev

Authors
  1. S. V. Yudintsev
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  2. A. A. Shiryaev
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Correspondence to S. V. Yudintsev.

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Translated by E. Glushachenkova

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Yudintsev, S.V., Shiryaev, A.A. Thermal Stability of Glass with Simulators of Chloride Highly Radioactive Wastes. Dokl. Phys. 63, 513–516 (2018). https://doi.org/10.1134/S1028335818120042

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  • DOI: https://doi.org/10.1134/S1028335818120042

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