• Nuclear Engineering and Technology
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• 제55권3호
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• pp.1191-1198
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• 2023

Bentonite buffer material is a critical component in an engineered barrier system (EBS) for disposing high-level radioactive waste (HLW). The bentonite buffer material protects the disposal canister from groundwater penetration and releases decay heat to the surrounding rock mass; thus, it should possess high thermal conductivity, low hydraulic conductivity, and moderate swelling pressure to safely dispose the HLWs. Bentonite clay is a suitable buffer material because it satisfies the safety criteria. Several additives have been suggested as mixtures with bentonite to increase the thermal-hydraulic-mechanical-chemical (THMC) properties of bentonite buffer materials. Therefore, this study investigated the geotechnical, mineralogical, and THMC properties of several candidate additives such as sand, graphite, granite, and SiC powders. Datasets obtained in this study can be used to select adequate additives to improve the THMC properties of the buffer material.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2002년도 봄 학술발표회 논문집
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• pp.19-26
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• 2002

In this paper, the nonlinear structural analysis for the composite structure of the spent nuclear fuel disposal container and the 50cm thick bentonite buffer is carried out to predict the collapse of the container while the sudden rock movement of 10cm is applied on the composite structure. This sudden rock movement is anticipated by the earthquake etc. at a deep underground. Horizontal symmetric rock movement is assumed in this structural analysis. Elastoplastic material model is adopted. Drucker-Prager yield criterion is used for the material yield prediction of the bentonite buffer and von-Mises yield criterion is used for the material yield prediction of the container(cast iron insert, copper outer shell and lid and bottom). Analysis results show that even though very large deformations occur beyond the yield point in the bentonite buffer, the container structure still endures elastic small strains and stresses below the yield strength. Hence, the 50cm thick bentonite buffer can protect the container safely against the 10cm sudden rock movement by earthquake etc.. Analysis results also show that bending deformations occur in the container structure due to the shear deformation of the bentonite buffer. The elastoplastic nonlinear structural analysis for the composite structure of the container and the bentonite buffer is performed using the finite element analysis code, NISA.

• 소성∙가공
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• 제12권5호
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• pp.479-486
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• 2003

This paper presents an elastoplastic analysis for spent nuclear fuel disposal container and its 50 cm thick bentonite buffer to predict the collapse of the container while the horizontal asymmetric sudden rock movement of 10 cm is applied on the composite structure. This sudden rock movement is anticipated by the earthquake etc. at a deep underground. Elastoplastic material model is adopted. Drucker-Prager yield criterion is used for the material yield prediction of the bentonite buffer and von-Mises yield criterion is used for the material yield prediction of the container. Analysis results show that even though very large deformations occur beyond the yield point in the bentonite buffer, the container structure still endures elastic small strains and stresses below the yield strength. Hence, the asymmetric 50 cm thick bentonite buffer can protect the container safely against the 10 cm sudden rock movement by earthquake etc.. Analysis results also show that bending deformations occur in the container structure due to the shear deformation of the bentonite buffer. The finite element analysis code, NISA, is used for the analysis.

• 방사성폐기물학회지
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• 제20권2호
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• pp.185-192
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• 2022

A compacted bentonite buffer is a major component of engineered barrier systems, which are designed for the disposal of high-level radioactive waste. In most countries, the target temperature required to maintain safe functioning is below 100℃. If the target temperature of the compacted bentonite buffer can be increased above 100℃, the disposal area can be dramatically reduced. To increase the target temperature of the buffer, it is necessary to investigate its properties at temperatures above 100℃. Although some studies have investigated thermal-hydraulic properties above 100℃, few have evaluated the water suction of compacted bentonite. This study addresses that knowledge gap by evaluating the water suction variation for compacted Korean bentonite in the 25-150℃ range, with initial saturations of 0 and 0.22 under constant saturation conditions. We found that water suction decreased by 5-20% for a temperature increase of 100-150℃.

• 터널과지하공간
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• 제21권4호
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• pp.264-273
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• 2011

고준위폐기물처분장에서 벤토나이트완충재는 공학적방벽의 중요한 구성요소 중 하나이다. 벤토나이트완충재는 방사성폐기물로부터의 붕괴열, 주위 암반으로부터의 지하수 유입, 고밀도로 압축된 벤토나이트 자체의 높은 팽윤압에 의해 큰 영향을 받는다. 그러므로 벤토나이트완충재의 열-수리-역학적 특성 이해와 평가모델의 입력데이터 확보는 고준위폐기물처분장의 성능 및 안전성 평가를 위해서 선행되어야 할 중요한 과제이다. 본 논문에서는 우리나라 고준위폐기물처분장 완충재 후보물질을 대상으로 지금까지 수행된 열-수리-역학적 특성을 분석하고, 기준벤토나이트완충재 조건을 설정하여, 이 조건에 부합되는 벤토나이트완충재의 열-수리-역학적 특성치를 제시하였다.

• 터널과지하공간
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• 제33권4호
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• pp.228-243
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• 2023

벤토나이트는 팽윤 능력과 낮은 투수율 등의 유리한 특성으로 인해 고준위방폐물처분장에서 완충재로 널리 인정받고 활용되고 있으며, 낮은 투수율로 인해 방사성 핵종이 주변 암반으로 이동하는 것을 효과적으로 방지하여 방사성 폐기물의 안전한 처분을 보장하는 데 중요한 역할을 한다. 그러나 벤토나이트 완충재의 장기적인 성능은 여전히 지속적인 연구의 대상으로 남아 있으며, 주요 우려 사항 중 하나는 벤토나이트의 팽윤과 지하수 흐름에 의한 완충재의 침식이다. 벤토나이트 완충재의 침식은 완충재의 무결성을 손상시키고 지하수를 통한 방사성 핵종의 이동을 촉진할 수 있는 콜로이드 형성을 초래하여, 결과적으로 방사성 핵종 이동 위험을 높임으로써 처분장 안전에 중대한 영향을 미칠 수 있다. 따라서 벤토나이트 완충재의 침식 메커니즘과 침식 정도를 수치 해석적으로 정량화하여 장기적인 벤토나이트 완충재의 성능 및 콜로이드 형성 정도를 평가하는 것이 고준위방폐물처분장의 안전성 평가에 매우 중요하다. 본 기술 보고에서는 동적 벤토나이트 확산 모델을 기반으로 거동이 유사한 영역을 두 개로 분류하여 벤토나이트의 균열 침투 및 콜로이드 형성을 모사할 수 있도록 제안된 모델인 Two-region 모델을 소개하였으며, 이 모델을 이용해 벤토나이트 완충재 침식 정도를 정량적으로 평가하였다.

• Nuclear Engineering and Technology
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• 제31권6호
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• pp.39-50
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• 1999

The physicochemical, mineralogical, hydraulic, swelling and mechanical properties of a domestic bentonite for use as the buffer material in a high-level waste repository have been measured. The bentonite is identified to be a Ca-bentonite, and the hydraulic conductivity of the compacted bentonite with the dry density higher than 1.4 Mg/㎥ is lower than 10$^{-11}$ m/s When the dry densities are 1.4 to 1.8 Mg/㎥, the swelling pressures are in the range of 6.6 to 143.5 kg/$\textrm{cm}^2$. The unconfined compressive strength is about 94 kg/$\textrm{cm}^2$, and the coefficient of volume change and the coefficient of consolidation are in the range of 0.O0249 to 0.02142 $m^2$/MN and 0.018 to 0.115$m^2$/year, respectively.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1495-1506
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• 2023

For the safe disposal of high-level radioactive waste using Engineered Barrier Systems (EBS), bentonite buffer is used by its high swelling capability and low hydraulic conductivity. When the bentonite buffer is contacted to heated pore water containing ions by radioactive decay, chemical alterations of minerals such as illitization reaction occur. Illitization of bentonite indicates the alteration of expandable smectite into non-expandable illite, which threatens the stability and integrity of EBS. This study intends to provide a thorough review on the information underlying in the illitization of bentonite, by covering basic clay mineralogy, smectite expansion, mechanisms and observation of illitization, and illitization in EBS. Since understanding of smectite illitization is crucial for securing the safety and integrity of nuclear waste disposal systems using bentonite buffer, this thorough review study is expected to provide essential and concise information for the preventive EBS design.

• 터널과지하공간
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• 제20권4호
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• pp.284-291
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• 2010

현재 제안되고 있는 고준위폐기물 심지층처분장의 설계에 따르면, 완충재와 뒷채움재의 재료로 벤토나이트 및 벤토나이트-모래 혼합물이 고려되고 있다. 후보물질인 경주벤토나이트를 대상으로, 압축 벤토나이트와 벤토나이트-모래 혼합물의 열전도도를 측정하였다. 경주벤토나이트와 벤토나이트-모래 혼합물의 열전도도를 건 조밀도, 함수비 및 모래 함량의 함수로서 예측할 수 있는 관계식을 제안하였다. 제안된 관계식은 실험 조건 하에서 열전도도를 10% 이내의 오차로 예측할 수 있다.

• Nuclear Engineering and Technology
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• 제31권2호
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• pp.139-150
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• 1999

The swelling pressure of a potential buffer material was measured and the effect of dry density, bentonite content and initial water content on the swelling pressure was investigated to provide the information for the selection of buffer material in a high-level waste repository. Swelling tests were carried out according to Box-Behnken's experimental design. Measured swelling pressures were in the wide range of 0.7 Kg/$\textrm{cm}^2$ to 190.2 Kg/$\textrm{cm}^2$ under given experimental conditions. Based upon the experimental data, a 3-factor polynomial swelling model was suggested to analyze the effect of dry density, bentonite content and initial water content on the swelling pressure The swelling pressure increased with an increase in the dry density and bentonite content, while it decreased with increasing the initial water content and, beyond about 12 wt.% of the initial water content, levelled off to nearly constant value.