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Proceedings of the National Academy of Sciences of Belarus. Physical-technical series

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The effect of model mineralized solution on diffusion of 137Cs and 85Sr in the clay from “Markovskoe” deposit when used in near-surface radioactive waste disposal

https://doi.org/10.29235/1561-8358-2026-71-1-79-88

Abstract

 The migration of radionuclides 137Cs and 90Sr in a compacted clay sample from the “Markovskoye” deposit of the Gomel region depending on the mineralization of its pore solution has been studied by the in-diffusion method. Distilled water and model mineralized solution were added to clay; the mineralized solution was modeling the chemical composition of pore water of the clay sample in case of atmospheric precipitation permeation into the radioactive waste disposal site and its consecutive passage through the materials of the physical barriers: concrete – Na-bentonite – concrete. The apparent diffusion coefficients (Da) of 137Cs and 90Sr in the clay sample were determined by the results of experiments: (1.5 ± 0.1) · 10–12 m2/s for 137Cs and (3.8 ± 0.2) · 10–11 m2/s for 85Sr in distilled water, (1.6 ± 0.1) · 10–12 m2/s for 137Cs and (6.3 ± 0.3) · 10–11 m2/s for 85Sr in mineralized solution. It was found that with increasing mineralization of the pore solution of the clay sample Da 90Sr increases by 1,7 times, and Da 137Cs does not change within the limits of the error of the experiments. This change of 90Sr diffusion coefficient in clay should be taken into account in case of its use as a part of the underlying screen of the disposal site of low- and medium-active waste of NPP, as it will increase the probability of 90Sr migration beyond its limits. There is a necessity to come up with technological solutions to prevent or decrease water permeation into the radioactive waste disposal as well as increase the diffusion time by raising the thickness of the clay barrier. The results of the experiments in this study confirm that clay from the “Markovskoye” deposit of the Gomel region is promising for use as a compacted clay barrier in the radioactive waste disposal facility. 

About the Authors

A. A. Baklay
The Joint Institute for Power and Nuclear Research – Sosny of the National of the Academy of Sciences of Belarus
Russian Federation

Anatoly A. Baklay – Senior Researcher, Laboratory for Radiochemical Research of Natural Environments and Examination of Radioactive Materials  

PO Box 119, 220109, Minsk 



T. G. Leontieva
The Joint Institute for Power and Nuclear Research – Sosny of the National of the Academy of Sciences of Belarus
Russian Federation

Tatiana G. Leontieva – Head of the Laboratory for Radiochemical Research of Natural Environments and Examination of Radioactive Materials 

PO Box 119, 220109, Minsk 



N. A. Makovskaya
The Joint Institute for Power and Nuclear Research – Sosny of the National of the Academy of Sciences of Belarus
Russian Federation

Natalia A. Makovskaya – Cand. Sci. (Biology), Associate Professor, Scientific Secretary 

PO Box 119, 220109, Minsk 



A. S. Onischuk
The Joint Institute for Power and Nuclear Research – Sosny of the National of the Academy of Sciences of Belarus
Russian Federation

Anna S. Onischuk – Junior Researcher, Laboratory for Radiochemical Research of Natural Environments and Examination of Radioactive Materials  

PO Box 119, 220109, Minsk 



References

1. Gautschi A., Gaus I., Gimmi T., Mazurek M., Wersin P., Cathelineau M., Bath A. Applied geochemistry special issue on “Geochemistry of clays and clay rocks in the context of radioactive waste disposal”. Applied Chemistry, 2019, vol. 105, pp. 127–129. https://doi.org/10.1016/j.apgeochem.2019.05.001

2. Severin A. V., Gopun A. V., Vasil’ev A. N., Enikeev K. I. Diffusion and sorption of radioactivity and strontium in a porous sorbent based on hydroxyapatite. Radiochemistry, 2021, vol. 63, no. 1, pp. 51–55. https://doi.org/10.1134/s1066362221010082

3. Crovisier J. L., Advocat T., Dussoray J. Nature and role of natural alteration gels formed on the surface of ancient volcanic glasses. (Natural analogs of waste containment glasses). Jornal of Nuclear Materials, 2003, vol. 321, pp. 91–109. https://doi.org/10.1016/S0022-3115(03)00206-X

4. Schwyn B., Wersin P., Rüedi J., Schneider J., Altmann S., Missana T., Noseck U. FUNMIG Integrated Project results and conclusions from a safety case perspective. Applied Geochemistry, 2012, vol. 27, pp. 501–525. https://doi.org/10.1016/j.apgeochem.2011.09.018

5. Zhemzhurov M. L., Kuzmina N. D. Technical concept of disposal for very low-level, low-level and short-lived intermediate-level radioactive waste of the Belarusian NPP. Vestsi Natsyyanal’nai akademii navuk Belarusi. Seryya fizika-tekhnichnykh navuk = Proceedings of the National Academy of Sciences of Belarus. Physical-technical series, 2022, vol. 67, no. 1, pp. 105–118 (in Russian). https://doi.org/10.29235/1561-8358-2022-67-1-105-118

6. Anisimov N. A., Kyvaeev A. A. Numerical modeling of moisture transfer in structures of a near-surface radioactive waste disposal facility. Radioaktivnye othody = Radioactive Waste, 2022, no. 3 (20), 97–106 (in Russian). https://doi.org/10.25283/2587-9707-2022-3-97-106

7. Varlakova G. A., Ostashkina E. E., Golybeva Z. E. Evaluation of the antimigration properties of materials for buffer filling of a near-surface radioactive waste repository. Radiochemistry, 2013, vol. 56, pp. 109–113. https://doi.org/10.1134/s1066362214010214

8. Sharafutdinov R. B., Umanova O. N., Korzh V. I. Modeling of radionuclide diffusion from near-surface liquid RW storage facilities. Yadernaya i radiatsionnaya bezopasnost’ = Nuclear and Radiation Safety, 2008, no. 1, pp. 18–25 (in Russian).

9. Makovskaya N. A., Leontieva T. G., Baklay A. A. Clays of the Republic of Belarus as engineering barriers for disposal of radioactive waste. Vestsi Natsyyanal’nai akademii navuk Belarusi. Seryya fizika-tekhnichnykh navuk = Proceedings of the National Academy of Sciences of Belarus. Physical-technical series, 2023, vol. 68, nо. 3, pp. 252–264 (in Russian). https://doi.org/10.29235/1561-8358-2023-68-3-252-264

10. Suskin V. V., Kapyrin I. V., Baldyrev K. A. Approaches to geomigration modeling for safety assessment of RAW disposal site in the GERA calculation complex. Radioaktivnye othody = Radioactive Waste, 2023, no. 3 (24), pp. 117–125 (in Russian). https://doi.org/10.25283/2587-9707-2023-3-117-125

11. Garcia-Gutiérrez M., Cormenzana J. L., Missana T., Mingarro M., Molinero J. Overview of laboratory methods employed for obtaining diffusion coefficients in FEBEX compacted bentonite. Journal of Iberian Geology, 2006, vol. 32, no. 1, pp. 37–53.

12. Baborová L., Viglošová D. Vopálka D. Comparison of Sr transport in compacted homoionous Na and Ca bentonite using a planar source method evaluated at ideal and non-ideal boundary condition. Water, 2021, vol. 13, pp. 37–53. https://doi.org/10.3390/w13111520

13. Bogatov S. A., Neuvazhaev G. D., Konovalov V. Yu. The issue of selection of engineering barriers of near-surface RW disposal facility on the example of overflow scenario. Voprosy radiatsionnoi bezopasnosti = Radiation Safety Issues, 2019, no. 3, pp. 3–14 (in Russian).

14. Makovskaya N. A., Leontieva T. G., Baklay A. A., Kuzmuk D. A. Effect of mineralized solution on protective properties of clays in radioactive waste isolation. Vestsi Natsyyanal’nai akademii navuk Belarusi. Seryya fizika-tekhnichnykh navuk = Proceedings of the National Academy of Sciences of Belarus. Physical-technical series, 2024, vol. 69, no. 3, pp. 233–243 (in Russian). https://doi.org/10.29235/1561-8358-2024-69-3-233-243

15. Martynov K. V., Zakharova E. V., Dorofeev A. N., Zubkov A. A., Prishchep A. A. Use of clay materials to create protective barriers for radiation hazardous facilities Radioaktivnye othody = Radioactive Waste, 2020, no. 3 (12), pp. 39–53 (in Russian). https://doi.org/10.25283/2587-9707-2020-3-39-53

16. Post J. E., Bish D. L. Rietveld refinement of crystal structures using powder X-ray diffraction data Reviews in Mineralogy and Geochemistry, 1989, vol. 20, no. 1, pp. 277–308.

17. Doebelin N., Kleeberg R. Profex: a graphical user interface foe the Rietveld refinement program BGM. Journal of Applied Chemistry, 2015, vol. 48, part 5, pp. 1573–1580. https://doi.org/10.1107/S1600576715014685

18. Rumynin V. G. Experience in studying clay strata and crystalline massifs as geologic media for final isolation of RWs. Radioaktivnye othody = Radioactive Waste, 2017, no. 1 (1), pp. 42–53 (in Russian).

19. Karas Sharayu, Kumar Sumit, Bajpai P. K., Tomar B. S. Diffusion of Na (I), Ca (II), Cs (I), Sr (II) and Eu (III) in smectite rich natural clay. Journal of Environmental Radioactivity, 2016, vol. 151, part 1, pp. 218–233. https://doi.org/10.1016/j.jenvrad.2015.10.012


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ISSN 1561-8358 (Print)
ISSN 2524-244X (Online)