Abstract
High-level radioactive wastes of nuclear power engineering are vitrified for removal to deep underground repositories. Radionuclide decay leads to heating and crystallization of the vitrified wastes with deterioration of their ability to retain hazardous components. The model for vitrified Na–Al–P glass dissolution in water has been developed taking into account the experimental data. The objective of the model is to predict the behavior of the waste form in the repository.
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Funding
This work was carried out under a State Assignment of the Institute of Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry, Russian Academy of Sciences. The solution compositions were determined in the Analytics Center for Collective Use, Institute of Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry, Russian Academy of Sciences.
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Translated by E. Maslennikova
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Malkovskii, V.I., Yudintsev, S.V. A Leaching Model for “Aged” Sodium–Aluminophosphate Vitreous Waste Forms of Radionuclides. Dokl. Earth Sc. 496, 185–189 (2021). https://doi.org/10.1134/S1028334X21020100
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DOI: https://doi.org/10.1134/S1028334X21020100