• Nuclear Engineering and Technology
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• v.31 no.6
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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.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 1998.11a
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• pp.216-220
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• 1998

Experimental studies were carried out to investigate water diffusion in unsaturated compacted bentonite for a landfill of hazardous wastes. Water content distributions were measured and water diffusion coefficients were determined when the dry densities of compacted bentonite were in the range of 1.4 - 1.8 g/㎤. Resaturation times were also calculated to analyze the ability of the compacted bentonite to retard water movement. The results obtained were as follows: Diffusion model described properly the water migration in unsaturated compacted bentonite. Water diffusion coefficients ranged from 4.30$\times$10$^{-6}$ $\textrm{cm}^2$/sec to 1.93$\times$10$^{-6}$ $\textrm{cm}^2$/sec, and decreased with increasing the dry density. The dry density of compacted bentonite was found to be an important factor to control the resaturation time by water. This study suggests that the domestic compacted bentonite should be a good barrier material against water movement in a landfill of hazardous wastes.

• Nuclear Engineering and Technology
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• v.23 no.4
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• pp.410-419
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• 1991

Four domestic bentonite samples collected from the south-eastern area of Korea were identified as Ca-bentonite by analysing XRD-patterns and chemical compositions. By comparing the surface area, CEC and the swelling rate of these samples, Dong-Hae A was selected as a suitable sample for the investigation of distribution coefficients. Sorption equilibrium of Cs, Co and Am was reached in around 10 days, but that of Sr was found to be much earlier. From the measured distribution coefficients, the domestic bentonite was found to have high sorption capacity. In the effect of varying concentration on the distribution coefficient, the values of radionuclides peaked at about 10$^{-7}$ mo1/$\ell$ of concentration.

• Journal of the Korean Ceramic Society
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• v.16 no.4
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• pp.201-205
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• 1979

Domestic Yungil bentonite (montmorillonite) was treated with 1N sodium hydroxide solution in an autoclave at several temperatures, between 100 to 200℃, for 1 to 24 hrs. The products were examined by X-ray diffraction analysis. The following concecutive reaction was valid. montmorillonite→amorphous aluminosilicate→analcime The reaction rate constants k and k' at 200℃ were 0.35hr-1 and 0.22hr-1, respectively. The activation energies for the conversion from montmorillonite to amorphous aluminosilicate and from amorphous aluminosilicate to analcime were 10 kcal/mol and 12kcal/mol, respectively.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.135-147
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• 2016

The buffer in geological disposal system is one of the major elements to restrain the release of radionuclide and to protect the container from the inflow of groundwater. The buffer material requires long-term stability, low hydraulic conductivity, low organic content, high retardation of radionuclide, high swelling pressure, and high thermal conductivity. These requirements could be determined by the quantitative analysis results. In case of South Korea, the bentonites produced in Gyeongju area have been regarded as candidate buffer/backfill materials at KAERI (Korea Atomic Energy Research Institute) since 1997. According to the study on several physical and chemical characteristics of domestic bentonite in the same district, this is the Ca-type bentonite with about 65% of montmorillonite content. Through this study, we present the criteria for the performance evaluation items and methods when collecting new buffer/backfill materials.

• Journal of Korea Foundry Society
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• v.9 no.5
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• pp.403-412
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• 1989

This study has been carried out to investigate into the properties of molding sands containing various core sands, $CO_2$, Shell, Furan, Pep Set and Cold Box, in the system sands using domestic active bentonite. The properties of system sands with 5% bentonite and 3% moistures containing baked core sands and no-baked core sands were varied by the ratio of core sands. The system sand containing no-baked core sands had been the poor bonding force and rough grain surface than those of the baked core sands. The L. O. I of system sand containing 30% organic binders core sands were more than inorganic binders core sands. It has been found that the no-baked core sands were necessary have to reclaim for using molding sand.

• Journal of the Mineralogical Society of Korea
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• v.19 no.2 s.48
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• pp.89-98
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• 2006

The thermal conductivities of bentonite blocks with various dry densities (1.6 and $1.8g/cm^3$), water contents (5, 9.4, 15, 20 wt%) and sand contents (0, 10, 20, 30 wt%) were measured in order to investigate the improvement in physical performance of buffer as an engineered barrier. The raw material was domestic bentonite from Oksan mine located in Gyeongju city. The increase in water content was most effective for improving the thermal conductivity. Especiallly, the bentonite blocks with more than 15 wt% of water content showed more than 1.0 W/mK values of thermal conductivity regardless of their dry densities and sand contents. Therefore, if the domestic Oksan bentonite is used as a buffer material, we can suggest that the manufacture of bentonite block having dry density of $1.6g/cm^3$, sand content of $10{\sim}30$ wt% and water content of 15 wt% will be most effective considering the easiness of a manufacturing of bentonite block and the efficiency of an increase in the thermal conductivity.

• Journal of Radiation Protection and Research
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• v.16 no.2
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• pp.27-39
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• 1991

The diffusion of Sr-85, Cs-137, Co-60 and Am-241 in compacted domestic bentonite was studied, using a diffusion cell unit in which diffusion took place axially from the center of cylindrical bentonite sample body. The effects of compaction density and heat-treated bentonite on diffusion were analysed. And the diffusion mechanism of radionuclide was also analysed by evaluating the measured diffusivity of anion Cl-36. The apparent diffusivities obtained for Sr-85, Cs-137, Co-60 and Am-241 were $l.07{\times}10^{-11},\;6.705{\times}10^{-13},\;l.226{\times}10^{-13}\;and\; l.310{\times}10^{-14}m^2/sec$, respectively. When the as-pressed density of bentonite increased from $1.8\;to\;2.0g/cm^3$, the apparent diffusivity of Cs-137 decreased by quarter. In the case of bentonite heat-treated to $150^{\circ}C$, no significant change in diffusivity was observed, which showed the possibility that the domestic bentonite could be used as a chemical barrier to retard the radionuclide migration at below $150^{\circ}C$. From the calculated pore and surface diffusivity, the surface diffusion due to the concentration gradient of radionuclide sorbed on the solid phase was found to dominate greatly in total transport process.

• Journal of the Korean Solar Energy Society
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• v.33 no.1
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• pp.66-72
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• 2013

In this study, the thermal conductive characteristics and basic properties of the nine commercial products of bentonite grouts were studied. Six of the nine products for ground heat exchanger systems are imported and others for civil engineering are domestic. The thermal conductivities of all bentonite products are nearly similar among products. The free swell indexes, viscosities and filter losses of the ground heat exchanger grouts are lower than those of the civil engineering ones. These characteristics seem to increase of the fluidity to fill the bentonite slurry to bore-hall perfectly, rather than to prevent underground water penetration. Thus, the mixtures of bentonites and sands are recommended for high thermal conduction grouts.

• Nuclear Engineering and Technology
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• v.30 no.1
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• pp.1-7
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• 1998

Effects of pH, bentonite and Portland cement on the leaching of the simulated waste glass were investigated. The simulated waste glass showed the low leach rate in the neutral pH region, while the leach rate in both acidic and alkaline regions increased. Addition of bentonite to the leachant enhanced the leaching of the waste glass. When the waste glass was leached at 72$^{\circ}C$ for 36 days in the ground water with gel state Na-bentonite, approximately 2.2${\mu}{\textrm}{m}$ of the surface was corroded out and the large amount of Ti, Nd, and Zr was observed on the surface. The amount of B leached from the simulated waste glass in the presence of domestic bentonite was about three times higher than that in the presence of Aldrich bentonite as well as Portland cement.