방사성폐기물학회지 (Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT))

  • 제22권1호
  • /
  • Pages.17-25
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  • 2024
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  • 1738-1894(pISSN)
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  • 2288-5471(eISSN)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
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Thermal Influence on Hydraulic Conductivity in Compacted Bentonite: Predictive Modeling Based on the Dry Density-Hydraulic Conductivity Relationship

  • 투고 : 2023.12.07
  • 심사 : 2024.02.21
  • 발행 : 2024.03.30
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초록

Hydraulic conductivity is a critical design parameter for buffers in high-level radioactive waste repositories. Most employed prediction models for hydraulic conductivity are limited to various types of bentonites, the main material of the buffer, and the associated temperature conditions. This study proposes the utilization of a novel integrated prediction model. The model is derived through theoretical and regression analyses and is applied to all types of compacted bentonites when the relationship between hydraulic conductivity and dry density for each compacted bentonite is known. The proposed model incorporates parameters such as permeability ratio, dynamic viscosity, and temperature coefficient to enable accurate prediction of hydraulic conductivity with temperature. Based on the results obtained, the values are in good agreement with the measured values for the selected bentonites, demonstrating the effectiveness of the proposed model. These results contribute to the analysis of the hydraulic behavior of the buffer with temperature during periods of high-level radioactive waste deposition.

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과제정보

This research was supported by the Nuclear Research and Development Program of the National Research Foundation of Korea (2021M2E3A2041351) and Institute for Korea Spent Nuclear Fuel and National Research Foundation of Korea (2021M2E1A1085193).

참고문헌

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