• Journal of Soil and Groundwater Environment
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• v.7 no.1
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• pp.41-51
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• 2002

Recently, domestic waste landfills are constructed sometimes on seashore area to provide large landfill area. In order to strengthen the foundation of landfills and to prevent the infiltration of leachate through the bottom, many cases of constructing cement hardened liners on seashore clays are found. In these cases, it is possible to have cracks in the hardened liners due to settlement with waste load since the stiffness of the hardened liner Is greater than that of clay liners. In this study, the capability of Self-Sealing and Self-Healing (SSSH) liner made with a seashore clay in the metropolitan landfill to prevent the percolation of water and leachate is examined using flexible-wall permeameter test and using uniaxial compression test. Applicability of SSSH to weathered granitic soil is also examined for self-sealing capabilities. The result of Flexible permeameter test for SSSH with the seashore clay showed that permeability obtained was lower than permeability criteria of Korean waste management law. The permeability and strength characteristics of SSSH with granitic soil and bentonite showed better results than with the seashore clay.

• Journal of Environmental Health Sciences
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• v.30 no.5 s.81
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• pp.388-394
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• 2004

Seaweed waste(SWW) was used to improve the liner effect in recycling of dredged soil as the landfill liner. It was found that the compressive strength became somewhat lower when SWW was added than that was when Ordinary Port-land Cement(OPC) only was added. The permeability coefficient, however, became lower in this case which showed the lowest permeability coefficient when the addition of SWW was one percent. Hence, to comply with the regulations for the compression strength and permeability coefficient of landfill liner, the addition of OPC should be over eight percent and that of seaweed waste one percent. The results of leaching test showed that the solidified material was not against the laws of waste control, so it is possible to use as the landfill liner and to expect sufficient economic effects because wastes such as dredged soil and seaweed can be recycled.

• Journal of the Korean Ceramic Society
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• v.25 no.2
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• pp.101-110
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• 1988

In order to improve the physical properties of concrete used for treatment and disposal container of low-and intermediate-level radioactive wastes, OPC (ordinary portland cement), ACPC (asphalt coated portland cement) and EPC(epoxy-portland cement) concrete specimens were prepared, and the physical properties of each concrete specimen were tested. According to the experimental results, EPC concrete showed better physical properties than ACPC and OPC concrete, however, ACPC concrete proved to be a best material for treatment and disposal container of radwastes in view of economic aspect and physical properties.

• Resources Recycling
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• v.16 no.4
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• pp.40-46
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• 2007

This research constructed property analysis for an high additional value construction materials. We try to utilize by the addition material of soil stabilizer. It was described to the material properties analysis of a sludge. A sample used 4 kinds of filtration cake which occurs by 4 companies and 3 kinds of sludge before filtration. ph of a sludge, a particle analysis and a scanning electron microscope observation were performed. We analyzed on the chemical ingredient by XRF, the phase by XRD, observed and analyzed the thermo-property of the sludge and the amount of the volatile constituent by TG-DTA.

• Journal of Radiation Protection and Research
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• v.20 no.4
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• pp.237-243
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• 1995

An estimate is made on the potential generation rate of H: from radiolysis of the Paraffin-wax encapsulant Proposed for the solidified liquid concentrate wasteform. The results show that the radiolytic Production of $H_2$ from paraffin-wax-encapsulated waste is dominated by the radiation energy released from $^{60}Co$. The radiolytic production of $H_2$ will proceed at an initial rate equivalent to aproximately $4.4{\times}10^2cm^3yr^1$ in 200 litre drums that are partly filled with 120 litres of encapsulated waste. The gas production rate will fall to a value of $7.2cm^3yr^1$ after 100 years. The lower flammable limit for $H_2$ in air will be reached in about 25 years and the lower explosive limit for $H_2$ in air would not be reached in 1000years. The timescale in which these safety-related limits are reached is strongly dependent on the level of filling of each waste drum. A reduction of the air space inside each drum would reduce the time required to reach the lower flammable limit.

• Economic and Environmental Geology
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• v.39 no.2 s.177
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• pp.181-190
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• 2006

Garnet has been suggested as one of the most promising material for the immobilization of radionuclide in high level waste. But data on its chemical durability are sufficiently available. Accordingly, Gd and Ce garnets were synthesized as imitators for $Pu^{3+}\;and\;Pu^{4+}$ were synthesized, and their leaching rates, the parameters of the chemical durability were measured by changing the conditions. In distilled water, the ranges of leaching rates of Gd and Ce were $1.2{\times}10^{-4}{\sim}4.6{\times}10^{-6}g/m^2/day\;and\;7.5{\times}10^{-5}{\sim}1.8{\times}10^{-7}g/m^2/day$, respectively. A comparison with previous data suggests that the chemical durabilities of garnets synthesized from this study are superior to those of other waste forms. Additional leaching experiments were performed with 0.01M-HCl and 0.01M-NaOH solutions to see Gd and Ce leaching at acidic and alkalinity conditions. In 0.01 H-HCl solution, the ranges of leaching rates of Gd and Ce were $2.5{\times}10^{-1}{\sim}6.9{\times}10^{-3}g/m^2/day\;and\;3.7{\times}10^{-1}{\sim}3.1{\times}10^{-3}g/m^2/day$, respectively, while were $3.1{\times}10^{-4}{\sim}1.3{\times}10^{-6}g/m^2/day\;and\;1.8{\times}10^{-3}{\sim}0g/m^2/day$, respectively in 0.01M-NaOH solution. It is believed that leaching data can be used in understanding chemical durabilities of waste from garnets in acidic and alkaline conditions.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.296-296
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• 2009

산화물 사용후핵연료를 대상으로 하는 파이로 공정은 고온 용융염 매질에서 산화물을 금속으로 전환시키는 전해환원 공정으로부터 시작된다. 이후, 전해정련 공정이 도입되어 전해환원 공정에서 금속으로 환원된 생성물을 처리하게 된다. 전기화학적 공정인 이 두 공정에는 전류전달 매질인 전해질로 용융염이 사용된다. 그러나 전해환원 공정은 LiCl 염을 기반으로 하는 반면 전해정련은 LiCl-KCl 공융염 조건에서 운전하여 두 공정의 연계성 향상 및 공정 안정성 확보를 위해서는 전해환원 공정에서 생성되는 금속전환체에 존재하는 잔류염을 제거하는 공정의 도입이 두 공정사이에 고려되고 있다. 전해환원 공정에서 산화물이 금속으로 환원되는 동안 고체입자의 외형이 유지되며 따라서 제거된 산소에 의해 금속전환체에는 공극이 발생하게 된다. 또한, 전해환원에 도입되는 산화물의 물리적 형태가 분말 또는 펠렛 등 다양한 형태로 도입 가능하여 단위 입자들 사이에 많은 공극이 발생하게 된다. 이렇게 기존재하거나 또는 공정 운전에 의해 새롭게 생성된 공극에는 전해환원 매질인 LiCl 염이 침투하여 금속전환체는 염에 의해 젖게 되며 공정 종료시 고화되어 금속전환체에 포함된다. LiCl을 제거하기 위해서는 가열에 의한 증류가 연구되고 있다. 그러나 LiCl의 낮은 증기압에 의해 비교적 낮은 온도에서 증발시키기 위해서는 감압조건이 필수적으로 고려되어야 한다. 한국원자력연구원에서는 다공성 모의 금속전환체를 사용하여 LiCl에 의한 Wetting 후 적절한 증발 조건 결정을 목적으로 온도 및 압력 조건 설정을 위한 기초실험에 결과를 수행하였다. 본 연구의 기초 실험 결과 $700^{\circ}C$온도 조건과 감압조건이 잔류염 제거를 위한 공정조건임을 밝혔다. 또한 모의 금속전환체를 담고 있는 미세 다공성 Basket은 고온조건에서 공극의 변형에 의해 증발에 대한 저항으로 작용하여 증발 효율을 저하시키는 것으로 나타났다. 따라서 잔류염 제거를 위해서는 전해환원 Basket이 비교적 큰 공극을 지녀야 할 것으로 판단된다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.110-120
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• 2005

For utilizing vitrification to treat low and intermediate level waste, industrial pilot plant was designed and constructed in October 1999 at Daejon, Korea through the joint research program among NETEC, MOBIS and SGN. More than 70 tests were performed on simulated IER, DAW etc. including key nuclide surrogate(Cs, Co); this plant has been shown to vitrify the target waste effectively and safely, however, some dust are generated from the HTF(High Temperature Filter) as a secondary waste. In case of long term operation, it is also concerned that pipe plugging can be occurred due to deposited dust in cooling pipe namely, connecting pipe between CCM(Cold Crucible Melter) and HTF. In this regard, we have developed the special complementary system of the off-gas treatment system to recycle the dust from HTF to CCM and to remove the interior dust of cooling pipe. Main concept of the dust recycling is to feed the dust to the CCM as a slurry state; this system is regarded as of an important position in the viewpoint of volume reduction, waste disposal cost and glass melt control in CCM. The role of DRS(Dust Recycling System) is to recycle the major glass components and key nuclides; this system is served to lower glass viscosity and increase waste solubility by recycling B, Na, Li components into glass melt and also to re-entrain and incorporate into glass melt like Cs, Co. Therefore dust recycling is helpful to control the molten glass; it is unnecessary to consider a separate dust treatment system like a cementation equipment. The effects of Dust Cleaner are to prevent the pipe plugging due to dust and to treat the deposited dust by raking the dust into CCM. During the pilot vitrification test, overall performance assessment was successfully performed; DRS and Dust Cleaner are found to be useful and effective for recycling the dust from HTF and also removing the dust in cooling pipe. The obtained operational data and operational experiences will be used as a basis of the commercial facility.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2000.11a
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• pp.145-149
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• 2000

We performed the geotechnical experiments of the hydraulic conductivity and compressive strength test with the stabilized soil in the laboratory, proved that it is useful to use the stabilized soil as an alternative for natural clay soil. Also, for mixing adding materials in the stabilized soil, it was determined that 1) the optimal mixing ratio of cement : bentonite : stabilizing agent was 90:60:1 of mass ratio(kg) for 1㎥ with soil, 2) it was also possible to use low quality bentonite(B\circled2) classified by swelling grade because of little difference from results of the hydraulic conductivity and compressive strength test with high quality bentonite(B\circled1). According to the results of the fixation ability of heavy metals(Pb$^{2+}$, Cu$^{2+}$, Cd$^{2+}$, Zn$^{2+}$) with soil and additives, authors can conclude that the higher pH condition had the more removal efficiency of heavy metals. B\circled1 and cement had especially high removal efficiency of heavy metals in a whole pH because of high alkalinity.alinity.

• Nuclear Engineering and Technology
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• v.22 no.4
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• pp.315-325
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• 1990

The analytical repository source term (REPS) computer code is developed for the safety assessment of radioactive waste geologic repository. For reliable prediction of the leach rates for various radionuclides, degradation of concrete structures, corrosion rate of waste container, degree of corrosion on the container surface, and the characteristics of radionuclides are considered in this REPS code. For the validation of the radionuclide leach rates predicted by the REPS model, the calculated leach rates of Cs-137, Sr-85, and Co-60 are compared with two reported leaching test results. Cesium and strontium leach congruently, and the leaching test results of these species can be reproduced by the congruent leaching model included in the REPS model. In case of cobalt, the solid diffusion model is in good agreement with the leaching test results.