• Journal of Energy Engineering
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• v.3 no.1
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• pp.70-76
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• 1994

본 연구는 방사성 폐액의 처리를 목적으로 화학처리와 한외여과막(UF)의 결합공정에 의해서 세슘이온의 제거특성을 조사하였다. 이 공정은 대상핵종과 선택성이 크고 한외여과막에 의해서 분리가 가능한 거대분자를 주입하여 핵종을 결합시키고, 이를 한외여과막에 의해서 분리 제거하는 개념이다. 실험은 흡착제로서 K2Cu3(Fe(CN6)2)를 제조하여 주입하였고 회분식 UF stirred cell를 이용하였으며, 용액의 pH, 세슘이온의 농도 및 K2Cu3(Fe(CN6)2)의 농도에 따라 세슘이온의 제거효율을 측정하였다. 세슘의 제거효율은 pH 및 K2Cu3(Fe(CN6)2)의 몰비에 따라 결정되며, pH가 5∼6에서 높은 제거율을 나타내었고 Cs/K2Cu3(Fe(CN6)2)의 몰비가 1.5 이하에서 90% 이상 제거되었다. K2Cu3(Fe(CN6)2)에 대한 Cs의 결합특성은 Langmuir isotherm형태의 식으로 나타내어 평가하였으며, 이때 세슘이온의 최대 흡착용량은 1.72 mM/mM K2Cu3(Fe(CN6)2) 이었다.

• Journal of the Korean Chemical Society
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• v.28 no.1
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• pp.62-69
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• 1984

The reaction of toluene with ethanol was studied over various cation-exchanged pentasil zeolite catalysts. The toluene disproportionation reaction to produce xylenes increased with increasing reaction temperature and the activity of alkylation of toluene with ethanol showed maximum at around $400^{\circ}C$. Only Cs-ZSM-5 catalyst showed pronounced p-ethyltoluene selectivity increasing to 96% with increasing degree of Cs-exchange. The sorption rate of m-xylene was lower for Cs-exchanged ZSM-5 than H-ZSM-5 catalyst. These phenomena were interpreted in terms of shape selectivity arising from the partial blocking of channel intersections by large cesium ions.

• Journal of the Korean Chemical Society
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• v.27 no.2
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• pp.127-132
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• 1983

The catalytic activity of ZSM-5 catalyst for the disproportionation of toluene is dependent on the type of cation exchanged, the degree of ion-exchange and the reaction temperature. The activity increases in the order of alkaline-, alkali earth-, hydrogen, and rare-earth-exchanged ZSM-5 and decreases with increasing degree of cation exchange. Among the ion-exchanged ZSM-5 catalyst, only Cs-ZSM-5 shows predominant selectivity for p-xylene. The selectivity increases with increasing degree of $Cs^+$-exchange and decreasing reaction temperature. This phenomenon is interpreted in terms of shape selectivity arising from the partial blocking of channel intersections by large cesium ions.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.10a
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• pp.267-268
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• 2012

• Journal of the Korean Electrochemical Society
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• v.15 no.4
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• pp.256-263
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• 2012

This study was performed to investigate the separation of cesium cations by using an electrochemical ion exchanger of nickel hexacyanoferrate($KNiFe(CN)_6$) film electrode. Potential, current, and charge passing through the cyclic voltammograms were measured in singular and binary solutions of 1.0M $NaNO_3$ and 1.0M $CsNO_3$. Before and after each experiment, the structural morphology and atomic composition of $KNiFe(CN)_6$ were analyzed by SEM and EDS, respectively. The ion selectivity of $KNiFe(CN)_6$ was also observed by the voltammograms and atomic compositions measured in the solution alternated between sodium and cesium. As the result of this study, it was found that the electrically switched $KNiFe(CN)_6$ ion exchanger had the significant advantage of 40 times or longer durability than conventional organic or inorganic ion exchanger. It was also shown that the $KNiFe(CN)_6$ ion exchanger had high selectivity for cesium over sodium.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.339-340
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• 2016

• Economic and Environmental Geology
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• v.51 no.2
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• pp.113-120
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• 2018

Radioactive cesium($^{137}Cs$) can be released into the environment through severe nuclear accidents such as the Chernobyl and Fukushima, The $^{137}Cs$ is one of major monitoring radionuclides due to its chemical toxicity, ${\gamma}$ radiation and long half-life($t_{1/2}=30.2yrs$). It has been known well that illite adsorb selectively and strongly the cesium due to frayed edge sites. The quantity of the FES in the illite could be controlled by weathering processes. Therefore, this study was modified illite samples through artificial weathering in the laboratory to increase sorption efficiency for cesium. Abundant interlayer cations(i.e., K, Ca) were eluted within 1 day, while Si and Al were gradually released from the crystal structure. In addition, broad peaks of XRD indicated the occurrence of chemical weathering. The cesium sorption distribution coefficients increased up to approximately 2 times after the weathering. These results suggested that sorption capacity of illite could be enhanced for cesium through artificial weathering under low temperature.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.415-420
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• 1998

시판중인 대표적 유·무기이온교환수지를 이용하여 방사성폐액의 주 방사성핵종인 코발트와 세슘에 대하여 방사성패액에 함유되어 있는 대표적 일반이온인 나트륨이온이 이들의 이온교환에 미치는 영향을 분석하였다. 나트륨 존재 하에서 세슘이온에 대한 선택도와 수지단위 부피당 폐액 처리 부피는 무기이온교환수지인 DT 30과 Durasil 230이 가장 높으며 반면에 유기이온교환수지는 두 수치 모두 낮아서 유기이온교환수지는 저농도의 나트륨 이온을 갖는 증발기 응축수의 처리에는 적합하나 나트륨이온의 농도가 비교적 높은 폐액처리에는 적합하지 않으며, 또한 코발트 제거 면에서는 무기이온교환수지인 DT 10 보다 유기이온교환수지인 Amberlite IRN 77이 바람직하다는 결론을 얻었다.

• Journal of the Korean Chemical Society
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• v.46 no.6
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• pp.515-522
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• 2002

Solid beta-dicalcium silicate hydrate $(\beta-C_2SH)$ synthesized under hydrothermal conditions at $240^{\circ}C$ and Ca/Si=2 molar ratio shows cation exchange properties towards divalent metal cations such as Fe, Cu, Zn, Cd, or Pb. The ability of metal cation uptake by the solid was found to be in the order: $Fe^{2+}$〉$Cu^{2+}$〉$Zn^{2+}$〉$Cd^{2+}$ = $Pb^{2+}$. Cesium selectivity of the solid was demonstrated in the presence of univalent cation such as $Li^+$, $Na^+$ and $K^+$ and divalent cations such as $Ca^{2+}$, $Mg^{2+}$ and $Ba^{2+}$, which are one hundred times more concentrated than the $Cs^+$. The uptake of $Cs^+$ is maximum in the presence of $Mg^{2+}$ whereas it is minimum in the presence of $K^+$. The different affinities of ${\beta}-C_2SH$ towards divalent metal cations can be used for the separation of those ions. Due to its selectivity for cesium it can be used in partitioning of radioactive Cs+ from nuclear wastes containing numerous cations. The mechanism of the metal cation exchange and cesium selectivity reactions by the solid is studied.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.351-351
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• 2004

원자력연구소에서는 PWR 사용후핵연료를 건식 개질함으로써 관리 부피를 줄이고 안전상에 문제를 일으키는 고방사성 핵종인 세슘과 스트론튬 등을 선택적으로 제거하여 방사능 및 냉각부하를 줄일 수 있는 사용후핵연료 차세대관리 공정개발에 대한 연구를 수행하고 있다. 이는 세라믹 형태의 PWR 핵연료를 금속으로 전환시켜 관리하는 방법으로 금속전환체는 PWR 사용후핵연료와 비교하여 체적, 방사능 및 발열량을 약 1/4로 줄일 수 있는 이점이 있다.(중략)