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Conditioning of Spent Electrolyte Surrogate LiCl-KCl-CsCl Using Magnesium Potassium Phosphate Compound

Author

Listed:
  • Svetlana A. Kulikova

    (Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, 19 Kosygin st., 119991 Moscow, Russia)

  • Kseniya Yu. Belova

    (Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, 19 Kosygin st., 119991 Moscow, Russia)

  • Ekaterina A. Tyupina

    (Department of High Energy Chemistry and Radioecology, D. Mendeleev University of Chemical Technology of Russia (MUCTR), 125480 Moscow, Russia
    Department of Closed Nuclear Fuel Cycle Technology, National Research Nuclear University, 115409 Moscow, Russia)

  • Sergey E. Vinokurov

    (Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, 19 Kosygin st., 119991 Moscow, Russia)

Abstract

The current work was aimed at developing a new conditioning method of spent electrolyte-radioactive waste (RW) generated during the pyrochemical reprocessing of mixed nitride uranium-plutonium spent nuclear fuel. Magnesium potassium phosphate (MPP) compound samples were synthesized under solidification of the electrolyte surrogate solution in a LiCl-KCl-CsCl system. The phase composition and structure of obtained compounds were studied by XRD and SEM-EDS methods. It was found that the compounds possessed a high compressive strength of 17–26 MPa. Hydrolytic stability of the compounds was evaluated in accordance with the long semi-dynamic test GOST R 52126-2003 and with the static PCT test. The 137 Cs content in the leached solutions was determined by gamma-ray spectrometry, and other compound components were determined by ICP–AES and ICP–MS methods. The differential leaching rate of Cs at 25 °C from monolithic samples on the 91st day of samples contact with water was 5–11 × 10 −5 g/(cm 2 ·day) (GOST R 52126-2003), and was 4–29 × 10 − 7 g/(cm 2 ∙day) on the 7th day at 90 °C from crushed samples (PCT). The thermal stability of the compound at 180 °C and 450 °C was shown. The characteristics of the obtained MPP compound correspond to the current regulatory requirements for materials for RW conditioning.

Suggested Citation

  • Svetlana A. Kulikova & Kseniya Yu. Belova & Ekaterina A. Tyupina & Sergey E. Vinokurov, 2020. "Conditioning of Spent Electrolyte Surrogate LiCl-KCl-CsCl Using Magnesium Potassium Phosphate Compound," Energies, MDPI, vol. 13(8), pages 1-11, April.
  • Handle: RePEc:gam:jeners:v:13:y:2020:i:8:p:1963-:d:346330
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    Citations

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    Cited by:

    1. Svetlana A. Kulikova & Sergey S. Danilov & Kseniya Yu. Belova & Anastasiya A. Rodionova & Sergey E. Vinokurov, 2020. "Optimization of the Solidification Method of High-Level Waste for Increasing the Thermal Stability of the Magnesium Potassium Phosphate Compound," Energies, MDPI, vol. 13(15), pages 1-15, July.
    2. Nailia Rakhimova, 2022. "Recent Advances in Alternative Cementitious Materials for Nuclear Waste Immobilization: A Review," Sustainability, MDPI, vol. 15(1), pages 1-25, December.
    3. Anna V. Frolova & Svetlana A. Kulikova & Kseniya Y. Belova & Sergey S. Danilov & Sergey E. Vinokurov, 2022. "Behavior of Glass-like and Mineral-like Phosphate Compounds with an Immobilized Chloride Mixture in Hydrogen Peroxide Solutions," Energies, MDPI, vol. 15(17), pages 1-13, September.
    4. Anna V. Frolova & Sergey E. Vinokurov & Irina N. Gromyak & Sergey S. Danilov, 2022. "Medium-Temperature Phosphate Glass Composite Material as a Matrix for the Immobilization of High-Level Waste Containing Volatile Radionuclides," Energies, MDPI, vol. 15(20), pages 1-12, October.

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