• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.596-602
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• 1996

석탄화력발전소 폐기물인 석탄회로 포집한 세슘의 고온안정성 분석을 위하여 Cs/Al의 몰비를 0.1에서 1.5까지 변화시켜 제조한 시료를 TGA, XRD, SEM등으로 분석하였다. 몰비가 0.75이상에서부터 pollucite 상 이외에 CsAlSiO$_4$상이 나타나기 시작하였으며 몰비가 증가할수록 CsAlSiO$_4$상이 증가하였다. 몰비가 0.5까지 세슘의 휘발로 인한 무게감량은 없었고 0.75부터는 몰비가 증가할수록 무게감량이 증가하였다. 이는 몰비가 증가할수록 세슘 증기압이 큰 CsAlSiO$_4$상이 증가하기 때문인 것으로 사료된다.

• Proceedings of the Optical Society of Korea Conference
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• 2003.07a
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• pp.52-53
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• 2003

세슘 원자 주파수 표준기에서 사용되는 램지 방법은 세슘 원자 빔을 U-자형 마이크로파 공진기로 지나게 하여 마이크로파와 시간 간격을 두고 두 번 상호작용하게 함으로써 간섭형 원자 공진 신호를 얻는 방법이다(그림 1). 이 방법을 사용하면 그림 2와 같은 공진 신호를 얻는데 이를 램지 신호라 한다. 원자 주파수 표준기의 정확도 평가를 위해서는 사용된 세슘 원자 빔의 속도 분포를 알아야 하는데, 이 램지 신호를 이용하여 속도 분포를 구할 수 있다. (중략)

• Korean Journal of Mineralogy and Petrology
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• v.35 no.2
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• pp.101-109
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• 2022

The mobility and transport of radioactive cesium are crucial factors to consider for the safety assessment of high-level radioactive waste disposal sites in granite. The retardation of radionuclides in the fractured crystalline rock is mainly controlled by the hydrochemical condition of groundwater and surface reactions with minerals present in the fractures. This paper reports the experimental results of cesium sorption to the Wonju Granite, a typical Mesozoic granite in Korea, performed in an anaerobic chamber that mimics the anoxic environment of a deep disposal site. We measured the rates and amounts of cesium (¹³³Cs) removed by crushed granite samples in different electrolyte (NaCl, KCl, and CaCl₂) solutions and a synthetic groundwater solution, with variations in the initial cesium concentration (10^-5, 5×10^-6, 10^-6, 5×10^-7 M). The cesium sorption kinetic and isotherm data were successfully simulated by the pseudo-second-order kinetic model (r²= 0.99) and the Freundlich isotherm model (r²= 0.99), respectively. The sorption distribution coefficient of granite increased almost linearly with increasing biotite content in granite samples, indicating that biotite is an effective cesium scavenger. The cesium removal was minimal in KCl solution compared to that in NaCl or CaCl₂ solution, regardless of the ionic strength and initial cesium concentration that we examined, showing that K⁺ is the most competitive ion against cesium in sorption to granite. Because it is the main source mineral of K⁺ in fracture fluids, biotite may also hinder the sorption of cesium, which warrants further research.

• Journal of Korean Society of Environmental Engineers
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• v.38 no.1
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• pp.8-13
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• 2016

This study investigated the removal of a radioactive cesium ($Cs^+$) in the water at the water treatment processes. Since cesium is mostly present as the $Cs^+$ ion state in water, it is not removed by sand filtration, and coagulation with polyaluminum chloride (PACl), powdered activated carbon (PAC) and mixture of PACl and PAC. However, it is known that the removal rate of cesium increases as the turbidity increases in raw water. As the turbidity was adjusted by 74 NTU and 103 NTU using the surrounding solids near G-water intake and yellow soils, removal rate of cesium was about 56% and 51%, respectively. In case of a GAC filtration with supernatants after jar-mixing/setting was conducted, 80% of cesium is approximately eliminated. The experimental results show that it is efficient to get rid of cesium when the turbidity of the raw water is more than 80 NTU. In case of a GAC filtration, about 60% of cesium is removed and it is considered by the effect of adsorption. Cesium is not eliminated by microfiltration membrane while about 75% of cesium is removed by reverse osmosis.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.4
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• pp.329-333
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• 2005

To identify the effect of engineered barriers on the leach rate of cesium from spent PWR fuel under a synthetic granitic groundwater, the related leach tests with and without bentonite or metals have been performed up to about 6 years. The leach rates were decreased as a function of leaching time and then became a constant after a certain period. The period in a bare spent fuel was much longer than that with bentonite or metal sheets. The cumulative fraction of cesium released from the spent fuel with bentonite or with copper and stainless steel sheets was steadily increased, but the fraction from bare fuel was rapidly and then sluggishly increased. However, the values deducted its gap inventory from the cumulative fraction of cesium released from the bare fuel was almost very close to the others. These suggest that the initial release of cesium from bare fuel might be dependant on its gap inventory and the effect of engineered barriers on the long-term leach rate of cesium would be insignificant but the rate with engineered barriers could be reduced in the initial transient period due to their retardation effect. And the long-term leach rate of cesium from spent fuel in a repository would be approached to a constant rate of $2\times10^{-2}g/m^2-day$.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.1
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• pp.37-46
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• 2019

As candidates for accident-tolerant fuels, ceramic microcell fuels, which are distinguished by their peculiar microstructures, are being developed; these fuels have $UO_2$ grains surrounded by cell walls. They contribute to nuclear fuel safety by retention of fission products within the $UO_2$ pellet, reducing rod pressure and incidence of SCC failure. Cesium, a hazardous fission product in terms of amount and radioactivity, can be captured by chemical reactions with ceramic cell materials. The capture-ability of cesium therefore depends on the thermodynamics of the capturing reaction. Conversely, compositional design of cell materials should be based on thermodynamic predictions. This study proposes thermodynamic calculations to evaluate the cesium capture-ability of three ceramic microcell compositions: Si-Ti-O, Si-Cr-O and Si-Al-O. Prior to the calculations, the chemical and physical states of the cesium and the cell materials were defined. Then, the reactivity was evaluated by calculating the cesium potential (${\Delta}G_{Cs}$) and oxygen potential (${\Delta}G_{O_2}$) under simulated LWR circumstances of normal operation. Based on the results, cesium capture is expected to be spontaneous in all cell compositions, providing a basis for the compositional design of ceramic microcell fuels as well as a facile way for evaluating cesium capture.

• Journal of the Korea Organic Resources Recycling Association
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• v.31 no.3
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• pp.65-71
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• 2023

Cesium discharged from nuclear power plants requires technology for safely treating, due to its harmfulness to the human body. In this work, activated carbon impregnated with triethylenediamine (TEDA) process was applied to effectively remove cesium dissolved in aqueous solution. The surfaces on the activated carbon were chemically modified with various TEDA concentrations (2.5, 5.0, 7.5, 10.0, and 12.5%) and the optimal TEDA concentration was obtained to be 5.0% by the assessment for cesium removal efficiency. In addition, when 5.0% TEDA-impregnated activated carbon was used to treat 5.0 and 10.0 mg/L of cesium, the removal efficiency was 71.5% and 61.1%, respectively. Also, it was found to be the chemical adsorption from the adsorption kinetics experiment by temperature change. A novel remediation technology developed in this study could be practically employed for removing cesium contained in surface and ground water.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.1
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• pp.53-64
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• 2007

The dynamic release behavior of Cs from high burn-up spent PWR fuel was experimentally performed under the conditions of a thermal treatment process such as voloxidation and sintering conditions. In voloxidation process, influence of the oxidation and reduction atmosphere on the Cs release characteristic using fragment type of spent fuel heated up to $1,500^{\circ}C$ was compared. In sintering process, temperature history effect on Cs release behavior was evaluated using green pellet under 4% $H_2/Ar$ environment. Temperature range for complete Cs release from spent fuel fragment under voloxidation condition was about $800^{\circ}C{\sim}1,200^{\circ}C$, but that of green pellet under the reduction atmosphere was $1,100^{\circ}C{\sim}1,400^{\circ}C$. Key parameters on Cs release behavior from spent fuel was powder formation as well as the diffusion rate of Cs compound to grain boundary and fuel surface.

• Journal of Korean Society of Forest Science
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• v.98 no.6
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• pp.669-675
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• 2009

The purpose of this study was to examine the influence of land use change in the forest catchment on sedimentation rate at the outlets of rivers in Kushiro Mire that have been impacted by forest clearing, agricultural activity and river regulation. We analysed Caesium-137(Cs-137) concentration in sediment cores, and we estimated sedimentation rates and Cs-137 inventories over the last 50 years. Cs-137 from atomic bomb testing first entered the environment in 1954 which provides easily identifiable chronological markers in the sediment. Because Cs-137 is strongly absorbed into sediment particles, its redistribution occurs in association with sedimentary particles. Since the 1950s, the forest catchment areas draining into the mire have been developed intensively from forest areas to agricultural lands. The sediment accumulations at the outlets of rivers after 1954 ranged from 36 to 148 cm. The Cs-137 inventory is significantly greater than the reference sites which reflected natural accumulation conditions because sediment containing Cs-137 was carried from catchments into the outlets of the rivers. In addition, the Cs-137 inventory was correlated with the sedimentation rate. However, the Cs-137 inventories in Kuchoro and Kushiro river profiles were slowly increased with the sedimentation rates. This is because the sediment originating from scoured areas such as streambeds and banks contains a low level of Cs-137 concentration.

• Economic and Environmental Geology
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• v.41 no.6
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• pp.709-717
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• 2008

Rhizofiltration for cesium uptake by sunflowers (Helianthus annuus L.) and beans (Phaseolus vulgaris var.) was investigated for groundwater contamination. The cesium removal by sunflowers was greater than 98% of the total cesium in solution, and the uptake by beans was also greater than 99% within 24 hours of the rhizofiltration, showing that the rhizofiltration has a great capability to remove cesium from the contaminated water system. Experiments at various pH of solution indicated that a solution of pH $5{\sim}9$ yielded very high cesium accumulation in two plants. From the results of the analysis for cesium accumulation in plant parts, about 80% of cesium transferred into the plant from solution was accumulated in the root part and less than 20% of cesium existed in the shoot part (including leaves). Results suggest that only the roots of the fully grown plant used for rhizofiltration should be disposed or post-treated and thus the cost and time to treat massive amounts of grown plants could be dramatically reduced when sunflower and bean are used in the real field. The results of SEM and EDS analyses indicated that the most of cesium were accumulated in the root surface as a ionic phase rather than a soil precipitation phase.