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Feasibility Assessment on the Application of X-ray Computed Tomography on the Characterization of Bentonite under Hydration

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초록

Bentonite has been proposed as a buffer and backfill material for high-level radioactive waste repository. Under such repository environment conditions, bentonite is subjected to com- bined thermal, hydrological, mechanical, and chemical processes. This study evaluates the feasibility of applying X-ray CT technology on the characterization of bentonite under hyd- ration conditions using a newly developed testing cell. The cylindrical cell is made of platic material, with a removable cap to place the sample, enabling to apply vertical pressure on the sample and to measure swelling pressure. The hydration test was carried out with a sample made of Gyeonju bentonite, with a dry density of 1.4 g/cm3, and a water content of 20%. The sample had a diameter of 27.5 mm and a height of 34 mm. During the test, water was injected at a constant pressure of 0.207 MPa, and lasted for 7 days. After one day of hydration, bentonite swelled and filled out the space inside the cell. Moreover, CT histograms showed how the hydration process induced an initial increase and later progressive decrease on the density of the sample. Detailed profiles of the mean CT value, CT standard deviation, and CT gradient provided more details on the hydration process of the sample and showed how the bottom and top regions exhibited a decrease on density while the middle region showed an increase, especially during the first two days of hydration. Later, the differences in CT values with respect to the initial state decreased, and were small at the end of testing. The formation and later reduction of cracks was also characterized through CT scanning.

Abstract

Bentonite has been proposed as a buffer and backfill material for high-level radioactive waste repository. Under such repository environment conditions, bentonite is subjected to com- bined thermal, hydrological, mechanical, and chemical processes. This study evaluates the feasibility of applying X-ray CT technology on the characterization of bentonite under hyd- ration conditions using a newly developed testing cell. The cylindrical cell is made of platic material, with a removable cap to place the sample, enabling to apply vertical pressure on the sample and to measure swelling pressure. The hydration test was carried out with a sample made of Gyeonju bentonite, with a dry density of 1.4 g/cm3, and a water content of 20%. The sample had a diameter of 27.5 mm and a height of 34 mm. During the test, water was injected at a constant pressure of 0.207 MPa, and lasted for 7 days. After one day of hydration, bentonite swelled and filled out the space inside the cell. Moreover, CT histograms showed how the hydration process induced an initial increase and later progressive decrease on the density of the sample. Detailed profiles of the mean CT value, CT standard deviation, and CT gradient provided more details on the hydration process of the sample and showed how the bottom and top regions exhibited a decrease on density while the middle region showed an increase, especially during the first two days of hydration. Later, the differences in CT values with respect to the initial state decreased, and were small at the end of testing. The formation and later reduction of cracks was also characterized through CT scanning.

참고문헌 (12)

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  11. 유맑고밝게빛나라, "고준위폐기물 처분장의 완충재용 국내산 벤토나이트의 특성 측정", Journal of Nuclear Fuel Cycle and Waste Technology, 14(2), pp.135~147 (2016), 한국방사성폐기물학회
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관련 논문AI추천

Current Status of X-ray CT Based Non Destructive Characterization of Bentonite as an Engineered Barrier Material멜빈 디아즈, 김광염, 김주연, 김진섭, 이창수한국암반공학회 · 터널과 지하공간2021 · 제31권 제6호A Coupled Hydro-Mechanical Analysis of a Deep Geological Repository to Assess Importance of Mechanical Factors of Bentonite Buffer김민섭, 김민준, 이승래, 전윤수, 전준서한국암반공학회 · 터널과 지하공간2019 · 제29권 제6호Swelling and hydraulic characteristics of two grade bentonites under varying conditions for low-level radioactive waste repository designChang Hao-Chun, Chen I-Ting, Chung Chih-Chung, Cuo Che-Jui, Ren Guo-Liang한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제4호Bentonite as an engineered barrier material for nuclear waste repository - Geotechnical perspectives, key properties, knowledge gaps, and opportunitiesCalaunan Jose Maria Ferdinand Victoria, Eun Jongwan, Feng Yuan, Kim Seunghee, Kim Yong-Rak, Noh Dong-Hwa한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제10호우리나라 고준위폐기물처분장 기준벤토나이트완충재의열-수리-역학적 특성치권상기, 이재완, 조원진한국암반공학회 · 터널과 지하공간2011 · 제21권 제4호Investigation of the various properties of several candidate additives as buffer materials윤석, 김태현, 이기준, 장세은한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제3호

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