KR101068523B1 - Method For Removing Cobalt and Cesium From Radioactive Wastewater - Google Patents
Method For Removing Cobalt and Cesium From Radioactive Wastewater Download PDFInfo
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- KR101068523B1 KR101068523B1 KR1020090082125A KR20090082125A KR101068523B1 KR 101068523 B1 KR101068523 B1 KR 101068523B1 KR 1020090082125 A KR1020090082125 A KR 1020090082125A KR 20090082125 A KR20090082125 A KR 20090082125A KR 101068523 B1 KR101068523 B1 KR 101068523B1
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Abstract
본원발명은 방사성 폐액으로부터 코발트 및 세슘을 제거하는 방법에 관한 것으로서, 방사성 폐액 내의 Co2+ 농도가 25 ~ 100 mg/L이 되도록, 방사성 폐액에 비방사성 코발트 염을 첨가하고 급속교반하는 단계, 상기 비방사성 코발트 염이 첨가된 방사성 폐액에 포타슘페로시아나이드(potassium ferrocyanide, K4Fe(CN)6)를 첨가하고 급속교반하는 단계, 상기 포타슘페로시아나이드가 첨가된 방사성 폐액의 산도가 pH 8.5 ~ 10.5 이 되도록, 알칼리 용액을 첨가한 후 순차적으로 급속교반, 완속교반 및 정치하는 단계를 포함한다.The present invention relates to a method for removing cobalt and cesium from a radioactive waste solution, the method comprising the steps of adding a non-radioactive cobalt salt to the radioactive waste solution and rapidly stirring it so that the Co 2+ concentration in the radioactive waste solution is 25 to 100 mg / L, the Potassium ferrocyanide (K 4 Fe (CN) 6 ) is added to the radioactive waste solution to which the non-radioactive cobalt salt is added and rapidly stirred, and the acidity of the radioactive waste solution to which the potassium ferrocyanide is added is pH 8.5 to 10.5, the step of rapid stirring, slow stirring and standing sequentially after the addition of the alkaline solution.
본원발명에 의하면, 하나의 공정에 의해 방사성 폐액으로부터 핵종성분인 코발트 및 세슘을 높은 효율로 제거할 수 있다.According to the present invention, cobalt and cesium, which are nuclide components, can be removed from the radioactive waste liquid with high efficiency by one process.
방사성 폐액, 코발트 염, 포타슘페로시아나이드, 알칼리 용액 Radioactive waste, cobalt salt, potassium ferrocyanide, alkaline solution
Description
본원발명은 방사성 폐액으로부터 코발트 및 세슘을 제거하는 방법에 관한 것이다.The present invention relates to a method for removing cobalt and cesium from radioactive waste fluid.
방사성 토양은 토양세척법(soil washing), 동전기 수세법(electrokinetic flushing), 산 침출법(acid leaching) 등을 제염기술에 의해 제염되는 것으로 알려져 있다. 상기의 방사성 토양의 제염에 따라 방사성 폐액이 발생하게 되는데, 상기 방사성 폐액에는 여러 종류의 금속이온과 함께 방사능 핵종인 Co-60 및 Cs-137이 함유되어 있다. 따라서, 방사성토양을 제염하여 자체처분 가능한 수준으로 방사능을 저감하기 위해서는, 상기 방사성 폐액의 안정적인 처리 또한 고려되어야 한다.Radioactive soil is known to be decontaminated by decontamination techniques such as soil washing, electrokinetic flushing, acid leaching, and the like. Radioactive wastewater is generated according to the decontamination of the radioactive soil. The radioactive wastewater contains radionuclides Co-60 and Cs-137 together with various kinds of metal ions. Therefore, in order to reduce radioactivity to a level capable of self-disposal by decontaminating radioactive soils, stable treatment of the radioactive waste liquid should also be considered.
현재까지 개발 적용된 방사성 폐액의 처리기술에는 증발, 침전, 이온교환, 막여과 등이 있는데 폐액 내 함유되어 있는 핵종의 화학적 특성을 이해하고 적절한 처리방법을 선택할 필요가 있다. 특히, 방사성 폐액 내에 존재하는 Co2+의 경우, pH 9 이상의 조건에서 수산화물의 형태로 침전하기 때문에, 단순한 pH 조절만으로 침전제거가 가능한 것으로 알려져 있다. 그러나 침전 제거만으로 방사성 폐액 내에 함유되어 있는 Cs+를 제거하는 것은 불가능하다는 문제점이 있다.The techniques for the treatment of radioactive waste liquids developed so far include evaporation, sedimentation, ion exchange, and membrane filtration. It is necessary to understand the chemical properties of the nuclides contained in the waste liquid and to select appropriate treatment methods. In particular, Co 2+ present in the radioactive waste solution is known to be precipitated and removed by simple pH adjustment because it precipitates in the form of a hydroxide at a pH of 9 or more. However, there is a problem that it is impossible to remove Cs + contained in the radioactive waste liquid only by sediment removal.
상기 문제점을 해결하기 위한 본원발명은, Co2+의 알칼리 침전처리와 Cs+의 이온교환에 의한 흡착제거의 원리를 이용하여, 방사성 폐액으로부터 핵종성분인 코발트 및 세슘을 하나의 공정에 의해 제거하는 것을 목적으로 한다.The present invention for solving the above problems is to remove the cobalt and cesium, which is a nuclide component from the radioactive waste liquid by one process, using the principle of adsorption removal by alkali precipitation of Co 2+ and ion exchange of Cs + . The purpose.
상기 목적을 달성하기 위한 본원발명은 방사성 폐액 내의 Co2+농도가 25 ~ 100 mg/L이 되도록, 방사성 폐액에 비방사성 코발트 염을 첨가하고 급속교반하는 단계, 상기 비방사성 코발트 염이 첨가된 방사성 폐액에 포타슘페로시아나이드(potassium ferrocyanide, K4Fe(CN)6)를 첨가하고 급속교반하는 단계, 상기 포타슘페로시아나이드가 첨가된 방사성 폐액의 산도가 pH 8.5 ~ 10.5 이 되도록, 알칼리 용액을 첨가한 후 순차적으로 급속교반, 완속교반 및 정치하는 단계를 포함하는 방사성 폐액으로부터 코발트 및 세슘을 제거하는 방법을 제공한다.The present invention for achieving the above object is the step of adding a non-radioactive cobalt salt to the radioactive waste solution and rapidly stirring so that the Co 2 + concentration in the radioactive waste solution is 25 to 100 mg / L, the radioactive cobalt salt added radioactive Potassium ferrocyanide (K 4 Fe (CN) 6 ) is added to the waste liquid and rapidly agitated. An alkaline solution is added so that the acidity of the radioactive waste liquid to which the potassium ferrocyanide is added is pH 8.5 to 10.5. After that, the present invention provides a method for removing cobalt and cesium from a radioactive waste solution, which comprises the steps of rapid stirring, slow stirring, and standing.
본원발명에 의하면, 하나의 공정에 의해 방사성 폐액으로부터 핵종성분인 코발트 및 세슘을 동시에 제거할 수 있다.According to the present invention, cobalt and cesium, which are nuclide components, can be simultaneously removed from the radioactive waste liquid by one process.
또한, 본원발명에 의하면 방사성 폐액으로부터 코발트 및 세슘을 높은 효율 로 제거할 수 있다.In addition, according to the present invention, cobalt and cesium can be removed from the radioactive waste liquid with high efficiency.
본원발명은 방사성 폐액으로부터 코발트 및 세슘을 제거하는 방법에 관한 것으로서, 방사성 폐액 내의 Co2+ 농도가 25 ~ 100 mg/L이 되도록 방사성 폐액에 비방사성(non-radioactive) 코발트 염을 첨가하고 급속교반하는 단계, 상기 비방사성 코발트 염이 첨가된 방사성 폐액에 포타슘페로시아나이드(potassium ferrocyanide)를 첨가하고 급속교반하는 단계, 상기 포타슘페로시아나이드가 첨가된 방사성 폐액의 산도가 pH 8.5 ~ 10.5 이 되도록, 알칼리 용액을 첨가한 후 순차적으로 급속교반, 완속교반 및 정치하는 단계를 포함한다. The present invention relates to a method for removing cobalt and cesium from a radioactive waste liquid, wherein a non-radioactive cobalt salt is added to the radioactive waste liquid and rapidly stirred so that the Co 2+ concentration in the radioactive waste liquid is 25 to 100 mg / L. Step, adding a potassium ferrocyanide (potassium ferrocyanide) to the radioactive waste solution to which the non-radioactive cobalt salt is added and rapidly stirring, so that the acidity of the radioactive waste solution to which the potassium ferrocyanide is added is pH 8.5 ~ 10.5, After the addition of the alkaline solution, it comprises the steps of rapid stirring, slow stirring and standing.
상기 방법은 Co2+의 알칼리 침전처리와 Cs+의 이온교환에 의한 흡착제거의 원리를 이용하여 코발트 및 세슘을 동시에 공침하여 발생한 침전(K2Cs2Fe(CN)6, Co(OH)2)을 제거함으로써, 방사성 폐액으로부터 핵종성분인 코발트 및 세슘을 하나의 공정에 의해 제거하는 것이다. 이러한 내용을 화학 반응식으로 나타내면 다음과 같다.The method is based on the principle of alkali precipitation of Co 2+ and adsorption removal by ion exchange of Cs +. The precipitation produced by co-precipitation of cobalt and cesium simultaneously (K 2 Cs 2 Fe (CN) 6 , Co (OH) 2 ) By eliminating, the radionuclide cobalt and cesium from the radioactive waste liquid are removed by one process. This content is represented by the chemical reaction equation as follows.
(1) 제 1 반응식 : K2CoFe(CN)6 생성(1) Scheme 1: Formation of K 2 CoFe (CN) 6
Co2+ + K4Fe(CN)6 → 2K+ + K2CoFe(CN)6↓Co 2+ + K 4 Fe (CN) 6 → 2K + + K 2 CoFe (CN) 6 ↓
(2) 제 2 반응식 : 이온교환에 의한 Cs+ 제거 (2) Second Reaction Scheme: Cs + Removal by Ion Exchange
K2CoFe(CN)6↓ + 2Cs+ → K2Cs2Fe(CN)6↓ + Co2+ K 2 CoFe (CN) 6 ↓ + 2Cs + → K 2 Cs 2 Fe (CN) 6 ↓ + Co 2+
(3) 제 3 반응식 : Co2+ 알칼리 침전처리(3) Third Reaction Scheme: Co 2+ Alkali Precipitation Treatment
Co2+ + 2NaOH → 2Na+ + Co(OH)2↓Co 2+ + 2NaOH → 2Na + + Co (OH) 2 ↓
상기 비방사성 코발트 염은 CoCl2, Co(NO3)2 를 비롯한 다양한 형태의 비방사성 코발트 염이 사용될 수 있다. 실제로 방사성 폐액 내에 잔존하는 Co2+의 농도가 매우 낮기 때문에, 비방사성 코발트 염을 첨가하여 방사성 폐액 내의 Co2+의 농도를 일정한 정도로 유지해야 한다. 왜냐하면, 제 1 반응식의 방사성 폐액 내의 Co2+의 농도가 최소 25 mg/L로 존재해야만 상기의 제 2 반응식 및 제 3 반응식의 정반응이 순차적으로 일어날 수 있는 K2CoFe(CN)6가 형성되기 때문이다. The non-radioactive cobalt salt may be used in various forms of non-radioactive cobalt salt including CoCl 2 , Co (NO 3 ) 2 . In fact, since the concentration of Co 2+ remaining in the radioactive waste liquid is very low, a non-radioactive cobalt salt should be added to maintain the concentration of Co 2+ in the radioactive waste liquid to a certain degree. This is because when the concentration of Co 2+ in the radioactive waste solution of the first reaction scheme is present at least 25 mg / L, K 2 CoFe (CN) 6 is formed in which the forward reaction of the second and third reaction schemes can occur sequentially. Because.
도 1의 그래프는, 첨가되는 포타슘페로시아나이드(K4Fe(CN)6)의 양(mg)이 증가할수록 방사성 폐액 내에 잔존하는 Cs+ 농도가 감소하며, Cs 제거율(Removal efficiency)이 상승한다는 것을 보여준다. 또한, 도 2의 그래프는 방사성 폐액내의 Co2+ 농도가 최소 25 mg/L일 때부터 방사성 폐액으로부터 Cs 제거율(Removal efficiency)이 상승한다는 것을 보여준다.The graph of FIG. 1 shows that as the amount (mg) of potassium ferrocyanide (K 4 Fe (CN) 6 ) added increases, the Cs + concentration remaining in the radioactive waste solution decreases, and the Cs removal efficiency increases. Shows that In addition, the graph of FIG. 2 shows that the Cs Removal efficiency from the radioactive waste liquid rises when the Co 2+ concentration in the radioactive waste liquid is at least 25 mg / L.
상기 알칼리 용액은 NaOH, KOH, Ca(OH)2를 비롯한 다양한 알칼리 용액이 사용될 수 있다.As the alkaline solution, various alkali solutions including NaOH, KOH, Ca (OH) 2 may be used.
상기 포타슘페로시아나이드가 첨가된 방사성 폐액 내의 포타슘페로시아나이드의 농도는 5 ~ 500 mg/L인 것이 바람직하다.The concentration of potassium ferrocyanide in the radioactive waste solution to which potassium ferrocyanide is added is preferably 5 to 500 mg / L.
상기 급속교반은 150 rpm 이상 800 rpm 미만의 속도로 5 ~ 10 분 동안 실행하는 것이 바람직하다.The rapid stirring is preferably performed for 5 to 10 minutes at a speed of 150 rpm or more and less than 800 rpm.
상기 완속교반은 20 rpm 이상 150 rpm 미만의 속도로 5 ~ 60 분 동안 실행하는 것이 바람직하다.The slow stirring is preferably performed for 5 to 60 minutes at a speed of 20 rpm or more and less than 150 rpm.
상기 정치는 10 ~ 120 분 동안 방치하는 것이 바람직하다.The stationary is preferably left for 10 to 120 minutes.
이하에서, 본원발명의 바람직한 실시예, 비교예를 참조하여 상세히 설명한다. 아래의 실시예, 비교예는 본원발명의 내용을 이해하기 위해 제시된 것일 뿐이며 당해 분야에서 통상의 지식을 가진 자라면 본원발명의 기술적 사상 내에서 많은 변형이 가능할 것이다. 따라서 본원발명의 권리범위가 이러한 실시예, 비교예에 한정되는 것으로 해석되어서는 안 된다.Hereinafter, with reference to the preferred examples, comparative examples of the present invention will be described in detail. The following examples and comparative examples are only presented to understand the content of the present invention, and those skilled in the art will be capable of many modifications within the technical spirit of the present invention. Therefore, the scope of the present invention should not be construed as being limited to these examples and comparative examples.
<실시예><Examples>
이하에서는, 도 3을 참조하여 본원발명에 따라 방사성 폐액으로부터 코발트 및 세슘을 제거하는 방법을 구체적으로 설명하고자 한다.Hereinafter, a method of removing cobalt and cesium from the radioactive waste solution according to the present invention will be described in detail with reference to FIG. 3.
먼저, 방사성 토양의 제염에 따라 발생된 방사성 폐액을 폐액 교반조에 흘려넣은 후, 상기 방사성 폐액 내의 Co2+ 농도가 25 mg/L이 되도록 비방사성 코발트 염(CoCl2 용액)을 첨가하고 150 rpm에서 5분 동안 급속교반 하였다.First, the radioactive waste liquid generated by the decontamination of the radioactive soil is poured into a waste agitating tank, and then a non-radioactive cobalt salt (CoCl 2 solution) is added so that the Co 2+ concentration in the radioactive waste liquid is 25 mg / L, and at 150 rpm. Rapid stirring for 5 minutes.
상기 비방사성 코발트 염이 첨가된 방사성 폐액에 포타슘페로시아나이드(K4Fe(CN)6)를 첨가하고 150 rpm에서 5분 동안 급속교반 하였다. 이때, 상기 포타슘페로시아나이드(K4Fe(CN)6)가 첨가된 방사성 폐액 내의 포타슘페로시아나이드(K4Fe(CN)6)의 농도는 160 mg/L가 되도록 하였다. Potassium ferrocyanide (K 4 Fe (CN) 6 ) was added to the radioactive waste solution to which the non-radioactive cobalt salt was added, followed by rapid stirring at 150 rpm for 5 minutes. In this case, the concentration of potassium ferrocyanide (K 4 Fe (CN) 6 ) in the radioactive waste solution to which potassium ferrocyanide (K 4 Fe (CN) 6 ) was added was 160 mg / L.
상기 포타슘페로시아나이드(K4Fe(CN)6)가 첨가된 방사성 폐액의 산도가 pH 9가 되도록, 알칼리 용액(NaOH 용액)을 첨가하였다. 그 후 순차적으로 150 rpm에서 5분 동안 급속교반하고 50 rpm에서 20분 동안 완속교반한 후, 상기 방사성 폐액을 폐액 침전조로 흘려보냈다. An alkaline solution (NaOH solution) was added so that the acidity of the radioactive waste solution to which the potassium ferrocyanide (K 4 Fe (CN) 6 ) was added was pH 9. Thereafter, the mixture was rapidly stirred at 150 rpm for 5 minutes and slowly stirred at 50 rpm for 20 minutes, and then the radioactive waste liquid was flowed into the waste liquid precipitation tank.
폐액 침전조에서 상기 방사성 폐액을 30분 동안 정치하면 침전 슬러지와 상징액(supernatant)로 나뉜다. 상기 상징액을 여과하여 남은 침전 슬러지는 탈수 및 건조하여 처리하였다. 상기 여과된 상징액에 대하여 MCA(Multi-Channel Analyzer)를 이용하여 방사능(Radioactivity)을 계측한 결과는 도 4에 나타냈다. If the radioactive waste liquid is allowed to stand for 30 minutes in the waste liquid sedimentation tank, it is divided into sediment sludge and supernatant. The supernatant was filtered and the remaining precipitate sludge was treated by dehydration and drying. The results of measuring radioactivity of the filtered supernatant using a multi-channel analyzer (MCA) are shown in FIG. 4.
도 4의 결과로부터 Co2+ 제거율, Cs+ 제거율을 하기의 식 1), 식 2)에 따라 계산한 결과 Co2+ 제거율은 99.2%이며, Cs+ 제거율은 98.9% 이었다.From the results of FIG. 4, the Co 2+ removal rate and the Cs + removal rate were calculated according to Equations 1) and 2) below. The Co 2+ removal rate was 99.2%, and the Cs + removal rate was 98.9%.
식 1)Equation 1)
식 2)Equation 2)
즉, 본원발명에 의하면 방사성 폐액으로부터 코발트 및 세슘을 제거율을 높일 수 있다.That is, according to the present invention, the removal rate of cobalt and cesium from the radioactive waste liquid can be increased.
<비교예>Comparative Example
방사성 폐액으로부터 코발트 및 세슘을 제거율을 살펴보기 위하여, 포타슘페로시아나이드(K4Fe(CN)6) 및 알칼리 용액을 사용하는 본원발명에 의하는 경우와, 단순히 알칼리 용액(NaOH)만을 사용하는 대조군에 의하는 경우를 비교하였다. 본원발명의 경우에는, 상기의 실시예와 동일한 방법으로 실험하였다.In order to examine the removal rate of cobalt and cesium from the radioactive waste solution, according to the present invention using potassium ferrocyanide (K 4 Fe (CN) 6 ) and an alkaline solution, and a control using only an alkaline solution (NaOH) only. The case was compared. In the case of the present invention, the experiment was carried out in the same manner as in the above embodiment.
대조군의 실험공정은 다음과 같다.Experimental process of the control is as follows.
먼저, 방사성 폐액의 산도가 pH 9가 되도록, 알칼리 용액(NaOH 용액)을 첨가하였다. 그 후 순차적으로 150 rpm에서 5분 동안 급속교반하고 50 rpm에서 20분 동안 완속교반한 후, 상기 방사성 폐액을 폐액 침전조로 흘려보냈다. 폐액 침전조에 서 상기 방사성 폐액을 30분 동안 정치하면 침전 슬러지와 상징액(supernatant)으로 나뉜다. 상기 상징액을 여과하여 남은 침전 슬러지는 탈수 및 건조하여 처리하였다. 상기 여과된 상징액에 대하여 MCA(Multi-Channel Analyzer)를 이용하여 방사능(Radioactivity)을 계측한 결과는 도 5에 나타냈다. First, an alkaline solution (NaOH solution) was added so that the acidity of the radioactive waste solution reached pH 9. Thereafter, the mixture was rapidly stirred at 150 rpm for 5 minutes and slowly stirred at 50 rpm for 20 minutes, and then the radioactive waste liquid was flowed into the waste liquid precipitation tank. The radioactive waste liquor is allowed to settle for 30 minutes in the waste liquor sedimentation tank and is divided into sediment sludge and supernatant. The supernatant was filtered and the remaining precipitate sludge was treated by dehydration and drying. The results of measuring radioactivity of the filtered supernatant using a multi-channel analyzer (MCA) are shown in FIG. 5.
본원발명의 경우, 도 5의 결과를 이용하여 상기의 식 1), 식 2)에 따라 계산한 결과, Co2+ 제거율은 99.2%, Cs+ 제거율은 98.9% 임을 알 수 있다. 또한, 대조군의 경우, 도 5의 결과를 이용하여 하기의 식 3), 식 4)에 따라 계산한 결과, Co2+ 제거율은 97.9%, Cs+ 제거율은 57.0% 임을 알 수 있다. In the present invention, as a result of calculating according to the above formula 1), formula 2) using the results of Figure 5, it can be seen that the Co 2+ removal rate is 99.2%, Cs + removal rate is 98.9%. In addition, in the case of the control group, the results of the calculation according to the following equations 3) and 4) using the results of Figure 5, it can be seen that the Co 2+ removal rate is 97.9%, Cs + removal rate is 57.0%.
식 3)Equation 3
식 4)
상기의 결과로부터, 방사성 폐액으로부터 코발트 및 세슘을 동시에 제거하기 위해서는 본원발명에 따라 포타슘페로시아나이드(K4Fe(CN)6) 및 알칼리 용액을 사용하는 것이 바람직하다는 것을 알 수 있다.From the above results, it can be seen that in order to simultaneously remove cobalt and cesium from the radioactive waste solution, it is preferable to use potassium ferrocyanide (K 4 Fe (CN) 6 ) and an alkaline solution according to the present invention.
이상 본 발명의 구체적 실시형태와 관련하여 본 발명을 설명하였으나 이는 예시에 불과하며 본 발명은 이에 제한되지 않는다. 당업자는 본 발명의 범위를 벗어나지 않고 설명된 실시형태를 변경 또는 변형할 수 있으며, 이러한 변경 또는 변형도 본 발명의 범위에 속한다. 또한, 본 명세서에서 설명한 각 구성요소의 물질은 당업자가 공지된 다양한 물질로부터 용이하게 선택하여 대체할 수 있다. 또한 당업자는 본 명세서에서 설명된 구성요소 중 일부를 성능의 열화 없이 생략하거나 성능을 개선하기 위해 구성요소를 추가할 수 있다. 뿐만 아니라, 당업자는 공정 환경이나 장비에 따라 본 명세서에서 설명한 방법 단계의 순서를 변경할 수도 있다. 따라서 본 발명의 범위는 설명된 실시형태가 아니라 특허청구범위 및 그 균등물에 의해 결정되어야 한다.The present invention has been described above in connection with specific embodiments of the present invention, but this is only an example and the present invention is not limited thereto. Those skilled in the art can change or modify the described embodiments without departing from the scope of the present invention, and such changes or modifications are within the scope of the present invention. In addition, the materials of each component described herein can be readily selected and substituted for various materials known to those skilled in the art. Those skilled in the art will also appreciate that some of the components described herein can be omitted without degrading performance or adding components to improve performance. In addition, those skilled in the art may change the order of the method steps described herein depending on the process environment or equipment. Therefore, the scope of the present invention should be determined by the appended claims and equivalents thereof, not by the embodiments described.
도 1은 첨가되는 포타슘페로시아나이드(K4Fe(CN)6)의 양과 Cs 제거율의 관계를 보여주는 그래프이다.1 is a graph showing the relationship between the amount of potassium ferrocyanide (K 4 Fe (CN) 6 ) added and the removal rate of Cs.
도 2는 방사성 폐액내의 Co2+의 농도와 Cs 제거율과의 관계를 보여주는 그래프이다.2 is a graph showing the relationship between the concentration of Co 2+ in the radioactive waste solution and the Cs removal rate.
도 3은 본원발명에 따라 방사성 폐액으로부터 코발트(Co) 및 세슘(Cs)을 제거하는 방법을 나타낸 개략도이다.Figure 3 is a schematic diagram showing a method of removing cobalt (Co) and cesium (Cs) from the radioactive waste solution according to the present invention.
도 4는 실시예의 방사능 계측 결과를 나타낸 것이다.4 shows the radioactivity measurement results of the example.
도 5는 비교예의 방사능 계측 결과를 나타낸 것이다.5 shows radioactivity measurement results of the comparative example.
Claims (5)
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| KR101429560B1 (en) * | 2013-01-11 | 2014-08-12 | 한국원자력연구원 | Manufacturing method of adsorbent based on magnetic nanoparticles for radioactive cesium |
| KR20150086665A (en) | 2014-01-20 | 2015-07-29 | 가톨릭관동대학교산학협력단 | Method of Removing Cesium from Wastewater by the Solidified Sericite |
| KR20150090464A (en) | 2014-01-29 | 2015-08-06 | 가톨릭관동대학교산학협력단 | Liquid Sericite Solution and Method of Removing Cesium from Contaminated Materials by the Same |
| KR20220122819A (en) | 2021-02-26 | 2022-09-05 | 주식회사 엘림글로벌 | Method and System for Decontamination of Contaminated Soil |
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| KR19990087589A (en) * | 1996-03-08 | 1999-12-27 | 스프레이그 로버트 월터 | Cesium ion adsorbent, its manufacturing method and method of use |
| KR20000021311A (en) * | 1998-09-28 | 2000-04-25 | 이종훈 | Calix[4]arene dibenzo crown ethers, their preparation process and their use for the selective extraction of cesium ion |
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| KR20000021311A (en) * | 1998-09-28 | 2000-04-25 | 이종훈 | Calix[4]arene dibenzo crown ethers, their preparation process and their use for the selective extraction of cesium ion |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| KR101429560B1 (en) * | 2013-01-11 | 2014-08-12 | 한국원자력연구원 | Manufacturing method of adsorbent based on magnetic nanoparticles for radioactive cesium |
| KR20150086665A (en) | 2014-01-20 | 2015-07-29 | 가톨릭관동대학교산학협력단 | Method of Removing Cesium from Wastewater by the Solidified Sericite |
| KR20150090464A (en) | 2014-01-29 | 2015-08-06 | 가톨릭관동대학교산학협력단 | Liquid Sericite Solution and Method of Removing Cesium from Contaminated Materials by the Same |
| KR20220122819A (en) | 2021-02-26 | 2022-09-05 | 주식회사 엘림글로벌 | Method and System for Decontamination of Contaminated Soil |
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