Черкаський бентоніт як компонент ізоляційних бар’єрів сховищ радіоактивних відходів
The article presents the results of determining the filtration properties of bentonite samples from the Cherkasy deposit (Ukraine) and its mixtures with fine-grained sand by measuring the filtration coefficient (cf) of water to analyze the effectiveness of engineered isolation barriers in near-surfa...
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| Datum: | 2025 |
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| Hauptverfasser: | , , , |
| Format: | Artikel |
| Sprache: | Ukrainian |
| Veröffentlicht: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2025
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| Online Zugang: | https://nuclear-journal.com/index.php/journal/article/view/1255 |
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| Назва журналу: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Zusammenfassung: | The article presents the results of determining the filtration properties of bentonite samples from the Cherkasy deposit (Ukraine) and its mixtures with fine-grained sand by measuring the filtration coefficient (cf) of water to analyze the effectiveness of engineered isolation barriers in near-surface radioactive waste repositories. A laboratory setup for permeability research and a corresponding measuring cell have been developed. Based on the obtained data, the dependence of сf on the hydraulic gradient indicators is shown. It was determined that сf of bentonite clay with a density of 1.5 g/cm3 at low values of the hydraulic gradient (less than 90) decreases to zero, and at a gradient from 91 to 184 it has practically a constant value of 1.3 · 10-12 m/s, which is consistent with the corresponding characteristics of the well-known bentonite MX 80 (Wyoming, USA) used to form engineered barriers in deep disposal facilities (Sweden, Finland). The сf value of the bentonite and sand mixture (mass ratio 20 : 80, density of 1.92 g/cm3) averages 2.2 · 10-10 m/s at a hydraulic gradient greater than 10, while at gradients less than 10, сf decreases sharply and drops to zero at a gradient less than 1. These values of сf for the bentonite and sand mixture are consistent with the corresponding characteristics of bentonite in various mixtures for the lower isolation barrier in near-surface radioactive waste repositories abroad, for example, in Great Britain, Spain and Sweden. The obtained results indicate the prospects for using domestic Cherkasy bentonite as an insulating material or its component in near-surface radioactive waste repositories. |
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