• 제목/요약/키워드: Radioactive concentration

검색결과 444건 처리시간 0.031초

고염/고방사성 폐액 내 Cs 제거를 위한 복합 흡착제 합성 및 특성 연구 (Study of Composite Adsorbent Synthesis and Characterization for the Removal of Cs in the High-salt and High-radioactive Wastewater)

  • 김지민;이근영;김광욱;이일희;정동용;문제권;현재혁
    • 방사성폐기물학회지
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    • 제15권1호
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    • pp.1-14
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    • 2017
  • 본 연구에서는 고염/고방사성 폐액 내 함유된 주요 고방사성핵종인 Cs 제거를 목적으로 고효율의 복합 흡착제(potassium cobalt ferrocyanide (PCFC)-loaded chabazite (CHA)) 합성 및 이의 적용성을 평가하였다. 복합 흡착제는 Cs을 비롯한 다른 입자를 수용할 수 있는 CHA를 지지체로 선정하였으며, $CoCl_2$$K_4Fe(CN)_6$ 용액의 단계적인 함침/침전을 통해 PCFC를 CHA 세공 내에 고정화함으로써 합성하였다. 복합 흡착제의 합성 시 평균 입자크기가 $10{\mu}m$ 이상의 CHA를 지지체로 사용할 경우, PCFC 입자는 안정적인 형태로 고정화되었다. 또한, 합성 시 복합 흡착제의 정제를 증가시키는 세척 방법을 최적화함으로써, 복합 흡착제의 물리적 안정성이 향상되었다. 최적의 합성법을 통해 얻은 복합 흡착제에 의한 Cs 흡착 시, 담수(무염조건) 및 해수(고염 조건)에서 모두 빠른 흡착 속도를 보였으며, 염 농도와 무관하게 비교적 높은 분배계수 값($10^4mL{\cdot}g^{-1}$ 이상)을 나타내었다. 그러므로, 본 연구에서 합성한 복합 흡착제는 CHA 및 PCFC가 각각 가지고 있는 물리적 안정성과 Cs에 높은 선택성 등을 고려하여 촤적화한 소재이며, 고염/고방사성폐액에 함유되어 있는 Cs을 고효율로 신속하게 제거할 수 있음을 알 수 있다.

원전 해체 시 방사성 콘크리트 폐기물 내부 방사능 분포 예측을 위한 컴프턴 영상 재구성 방법의 비교 (Comparison of Compton Image Reconstruction Algorithms for Estimation of Internal Radioactivity Distribution in Concrete Waste During Decommissioning of Nuclear Power Plant)

  • 이태웅;조성민;윤창연;김낙점
    • 방사성폐기물학회지
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    • 제18권2호
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    • pp.217-225
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    • 2020
  • 해체 원전에서 총 폐기물의 약 70~80%에 해당하는 많은 양의 콘크리트 폐기물은 해체 폐기물의 대부분을 차지한다. 해체 시 발생된 콘크리트 폐기물은 핵종별 농도에 따라 규제해제 폐기물과 방사성폐기물로 정의할 수 있다. 따라서, 방사성 콘크리트 폐기물의 처분 비용을 저감하기 위하여 자체 처분 및 제한적 재활용을 위한 제염 작업의 수행이 중요하다. 그러므로 콘크리트 폐기물의 효율적인 제염 작업을 위해 내부 방사능 분포를 예측하는 것이 필수적이다. 본 연구는 원전 해체 시, 발생되는 콘크리트 폐기물의 내부 방사능 분포를 예측하기 위하여 다양한 컴프턴 영상 재구성 방법의 성능을 비교하였다. 다양한 컴프턴 영상 재구성 방법으로 단순 역투사(SBP), 필터 후 역투사(FBP), 최대우도 기댓값 최대화 방법(MLEM), 그리고 기존의 MLEM의 시스템 반응 함수에 에너지 정보가 결합되어 확률적으로 계산하는 최대우도 기댓값 최대화 방법(E-MLEM)이 사용되었다. 재구성된 영상을 획득한 후, 정량적인 분석 방법을 이용하여 재구성된 영상의 성능을 정량적으로 비교 및 평가하였다. MLEM 및 E-MLEM 영상 재구성 방법은 각각 재구성된 영상에서 높은 이미지 분해능과 신호 대 잡음비를 유지하는 데 있어 가장 좋은 성능을 보여주었다. 본 연구에서 도출된 결과들은 원자력 시설 해체 시 방사성 콘크리트 폐기물의 내부 방사능 분포를 예측하기 위한 수단으로 컴프턴 영상을 사용할 수 있는 가능성을 보여주었다.

원전 중대사고시 피폭경로 및 핵종의 방사선 피폭에 대한 상대적 중요도 해석 (Analysis of Exposure Pathways and the Relative Importance of Radionuclides to Radiation Exposure in the Case of a Severe Accident of a Nuclear Power Plant)

  • 황원태;서경석;김은한;한문희;김병우
    • Journal of Radiation Protection and Research
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    • 제19권3호
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    • pp.209-221
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    • 1994
  • 원자력발전소의 중대 사고시 대기로 방출된 방사성물질에 의해 피폭자가 사고후 일생동안 받게 될 전신 피폭선량과 핵종의 상대적 중요도를 방출점으로부터 거리에 따라 각 피폭경로에 대해 평가하였다. 방사능운과 지표에 침적된 방사성물질에 의한 외부피폭, 호흡과 오염된 음식물섭취에 의한 내부피폭이 피폭경로로 고려되었다. 오염된 음식물섭취에 의한 영향은 우리나라 환경을 고려하여 개발된 동적 삽식경로모델 KORFOOD을 사용하여 침적시점과 침적후 시간에 따른 음식물내 방사성물질의 농도 변화를 고려하였다. 방출점으로부터 80km까지 피폭선량을 평가한 결과, 오염된 음식물섭취에 의한 영향이 가장 높았다. 핵종별 기여도는 방사능운에 의한 외부피폭과 호흡에 의한 내부피폭의 경우 I, 침적된 방사성물질에 의한 외부피폭의 경우 Cs에 의한 영향이 가장 높았다. 오염된 음식물섭취에 의한 내부피폭의 경우 Cs은 여름철 침적, Sr은 겨울철 침적에 보다 중요한 영향을 미쳤다.

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Assessment of Radionuclide Deposition on Korean Urban Residential Area

  • Lee, Joeun;Han, Moon Hee;Kim, Eun Han;Lee, Cheol Woo;Jeong, Hae Sun
    • Journal of Radiation Protection and Research
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    • 제45권3호
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    • pp.101-107
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    • 2020
  • Background: An important lesson learned from the Fukushima accident is that the transition to the mid- and long-term phases from the emergency-response phase requires less than a year, which is not very long. It is necessary to know how much radioactive material has been deposited in an urban area to establish mid- and long-term countermeasures after a radioactive accident. Therefore, an urban deposition model that can indicate the site-specific characteristics must be developed. Materials and Methods: In this study, the generalized urban deposition velocity and the subsequent variation in radionuclide contamination were estimated based on the characteristics of the Korean urban environment. Furthermore, the application of the obtained generalized deposition velocity in a hypothetical scenario was investigated. Results and Discussion: The generalized deposition velocities of 137Cs, 106Ru, and 131I for each residence type were obtained using three-dimensional (3D) modeling. For all residence types, the deposition velocities of 131I are greater than those of 106Ru and 137Cs. In addition, we calculated the generalized deposition velocities for each residential types. Iodine was the most deposited nuclide during initial deposition. However, the concentration of iodine in urban environment drastically decreases owing to its relatively shorter half-life than 106Ru and 137Cs. Furthermore, the amount of radioactive material deposited in nonresidential areas, especially in parks and schools, is more than that deposited in residential areas. Conclusion: In this study, the generalized urban deposition velocities and the subsequent deposition changes were estimated for the Korean urban environment. The 3D modeling was performed for each type of urban residential area, and the average deposition velocity was obtained and applied to a hypothetical accident. Based on the estimated deposition velocities, the decision-making systems can be improved for responding to radioactive contamination in urban areas. Furthermore, this study can be useful to predict the radiological dose in case of large-scale urban contamination and can support decision-making for long-term measurement after nuclear accident.

Preparation of Styrene-Ethyl acylate Core-shell Structured Detection Materials for aMeasurement of the Wall Contamination by Emulsion Polymerization

  • Hwang, Ho-Sang;Seo, Bum-Kyoung;Lee, Dong-Gyu;Lee, Kune-Woo
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.84-85
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    • 2009
  • New approaches for detecting, preventing and remedying environmental damage are important for protection of the environment. Procedures must be developed and implemented to reduce the amount of waste produced in chemical processes, to detect the presence and/or concentration of contaminants and decontaminate fouled environments. Contamination can be classified into three general types: airborne, surface and structural. The most dangerous type is airborne contamination, because of the opportunity for inhalation and ingestion. The second most dangerous type is surface contamination. Surface contamination can be transferred to workers by casual contact and if disturbed can easily be made airborne. The decontamination of the surface in the nuclear facilities has been widely studied with particular emphasis on small and large surfaces. The amount of wastes being produced during decommissioning of nuclear facilities is much higher than the total wastes cumulated during operation. And, the process of decommissioning has a strong possibility of personal's exposure and emission to environment of the radioactive contaminants, requiring through monitoring and estimation of radiation and radioactivity. So, it is important to monitor the radioactive contamination level of the nuclear facilities for the determination of the decontamination method, the establishment of the decommissioning planning, and the worker's safety. But it is very difficult to measure the surface contamination of the floor and wall in the highly contaminated facilities. In this study, the poly(styrene-ethyl acrylate) [poly(St-EA)] core-shell composite polymer for measurement of the radioactive contamination was synthesized by the method of emulsion polymerization. The morphology of the poly(St-EA) composite emulsion particle was core-shell structure, with polystyrene (PS)as the core and poly(ethyl acrylate) (PEA) as the shell. Core-shell polymers of styrene (St)/ethyl acrylate (EA) pair were prepared by sequential emulsion polymerization in the presence of sodium dodecyl sulfate (SOS) as an emulsifier using ammonium persulfate (APS) as an initiator. The polymer was made by impregnating organic scintillators, 2,5-diphenyloxazole (PPO) and 1,4-bis[5-phenyl-2-oxazol]benzene (POPOP). Related tests and analysis confirmed the success in synthesis of composite polymer. The products are characterized by IT-IR spectroscopy, TGA that were used, respectively, to show the structure, the thermal stability of the prepared polymer. Two-phase particles with a core-shell structure were obtained in experiments where the estimated glass transition temperature and the morphologies of emulsion particles. Radiation pollution level the detection about under using examined the beta rays. The morphology of the poly(St-EA) composite polymer synthesized by the method of emulsion polymerization was a core-shell structure, as shown in Fig. 1. Core-shell materials consist of a core structural domain covered by a shell domain. Clearly, the entire surface of PS core was covered by PEA. The inner region was a PS core and the outer region was a PEA shell. The particle size distribution showed similar in the range 350-360 nm.

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경주 중·저준위 방폐장의 수리지화학 및 통계 분석 (Hydrogeochemistry and Statistical Analysis for Low and Intermediate Level Radioactive Waste Disposal Site in Gyeongju)

  • 옥순일;김시은;정성연;이충모
    • 한국지구과학회지
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    • 제44권6호
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    • pp.629-642
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    • 2023
  • 국내 중·저준위 방사성폐기물은 영구적 격리를 위해 처분장에 매립하고 있으며 그 위치는 경주에 있다. 이러한 방사성폐기물의 영구적인 격리를 위한 처분시설은 공학적 방벽과 자연 방벽으로 구성되어 있으며 자연 방벽을 특성을 파악하기 위하여 한국원자력환경공단에서는 2006년부터 부지특성조사를 수행하였고, 이후 부지감시 및 조사계획에 따른 감시를 수행하여 부지특성의 변화를 지속적으로 확인하고 있다. 중저준위 방폐장의 수리지화학적 환경은 자연 방벽의 평가를 위해 중요한 요소로 손꼽히고 있으나 동해와 가까운 경주의 지역적 특성상 해수의 영향을 반드시 고려해야 한다. 따라서 본 연구에서는 처분 부지의 지하수 관정 7개 및 관정의 심도별 수질 자료를 취합해 지하수 자료 총 30개를 해수 2개소와 비교 분석하여 수리지화학적 환경을 해석하였다. 분석 자료는 수질 10개 항목(온도, EC, HCO3, Na, K, Ca, Mg, Cl, SO4, SiO2)을 2017년 3분기부터 2022년 3분기까지 총 5년간 20회의 자료를 활용하였다. 특히, EC, HCO3, Na, Cl의 농도 변화를 통해 연구 지역의 배경 농도 및 관정의 구간별 해수의 영향을 파악하였으며, 시계열 군집 분석을 통해 담수, 기수, 해수의 분류를 시도하였다. 그 결과, 기존의 모니터링 방법으로는 확인하지 못한 부지내 수리지화학적 변화를 제시하였다.

Effect of the Slag Former on the Metal Melting and Radionuclides Distribution in an Electric Arc Furnace

  • Song Song-Pyung;Min Byung-Youn;Choi Wang-Kyu;Chung Chong-Hun;Oh Won-zin
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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    • pp.32-37
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    • 2005
  • The characteristics of the metal melting and radionuclide distribution of the radioactive has been investigated in a lab-scale arc furnace. The slag former based on the constituents of silica, calcium oxide, aluminum oxide, borate and calcium fluoride additions was used for melting of the stainless and carbon steel. In the melting of the stainless steel, the amount of slag formation increased with an increase of the concentration of the slag former. But the effects of the slag basicity on the amount of stag formation showed a local maximum value of the slag formation with an increase of the basicity index in the melting of the stainless steel as well as in the melting of the carbon steel. With an increase of the amount of slag former addition, the trends of the cobalt distribution into the ingot and the stag depended on the kind of slag former used in the melting of the stainless steel while the effect of the slag basicity on the distribution of the cobalt was not clarified in the melting of carbon steel. Tn the melting of the carbon steel, the strontium was captured at up to $50\%$ into the slag phase. Cesium was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the dust phase.

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Selective adsorption of Cs+ by MXene (Ti3C2Tx) from model low-level radioactive wastewater

  • Jun, Byung-Moon;Jang, Min;Park, Chang Min;Han, Jonghun;Yoon, Yeomin
    • Nuclear Engineering and Technology
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    • 제52권6호
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    • pp.1201-1207
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    • 2020
  • This study explored whether MXene (Ti3C2Tx) could remove radioactive Cs+ from model nuclear wastewater. Various adsorption tests were performed and the physical aspects of the interaction were investigated. We varied the MXene dosage, Cs+ initial concentration, solution pH, solution temperature and exposure time. MXene adsorption exhibited very fast kinetics, based on the fact that equilibrium was achieved within 1 h. MXene exhibited an outstanding adsorption capacity (148 mg g-1) at adsorbent and adsorbate concentrations of 5 and 2 mg L-1, respectively, at neutral pH condition (i.e., pH 7). We explored Cs+ adsorption by MXene in the presence of four different ions (NaCl, KCl, CaCl2 and MgCl2) and three different organic acids (sodium oleate, oxalic acid, and citric acid). The Cs+ removal rate changed in the presence of these components; adsorption of Cs+ by MXene thus involved ion exchange, supported by both Fourier-transform infrared spectroscopy and X-ray photoelectron spectroscopy. We confirmed that MXene was re-usable for at least four cycles. MXene is cost-effective and practical when used to adsorb radionuclides (e.g., Cs+) in nuclear wastewater.

후쿠시마산(産) 농산물 수요감소에 대비한 농산물 수출전략 (Export Strategies Against Decreasing Demand of Fukushima's Agricultural Porducts)

  • 홍길종
    • 아태비즈니스연구
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    • 제9권2호
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    • pp.105-121
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    • 2018
  • In 1995, the WTO started to ease the trade barriers. Globalization has accelerated. The opening of the agricultural products market is rapidly gaining momentum with the conclusion of an FTA. The acceleration of this FTA is expected to be a threat to Korea's agriculture, and a new strategy is needed. At the beginning of the nuclear accident, mainly radioactive materials are found in the surface layer of the soil. Over time, the concentration of the plant gradually increases. After 5 years, it becomes noticeable. In March 2016, it will be five years after the nuclear accident. Radioactive contamination is very likely to occur in agricultural products produced in the Fukushima area at this time. In this period, agricultural products produced in the Fukushima region are expected to generate supply disruptions in Japan, and imports to replace them will increase. Therefore, it is necessary to establish a mid- and long-term strategy for exporting to Japan by analyzing the competitiveness of Korean agricultural products. In this study, standardization index was derived by using agricultural price ratio, TSI, export CAC. Based on this, we analyzed the competitiveness of each item in the Japanese market. The analysis shows that garlic is the most competitive product in the Japanese market. Also, strawberry, tomato, and cucumber were found to be competitive. On the other hand, Kiwi, pineapple, soybean, onion, potato, etc. As a result of the analysis, the following strategies were proposed for the export of agricultural products with high competitiveness. First, it is necessary to develop technology to suppress deterioration of export transportation quality. Second, continuous supply of local consumption pattern information is required. Third, it is necessary to expand exports by processing fresh food. Fourth, it suggested the establishment of export base and strengthening of support system.

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연소 조건과 수종을 달리한 블랙카본의 물리화학적 성질 및 세슘의 흡착 특성 (Physicochemical and Adsorptive Properties of Black Carbon for Radioactive Cesium under Various Combustion Conditions and Tree Species)

  • 전소담;정성욱;한원식;장경순;신우식;황정환
    • 한국물환경학회지
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    • 제33권6호
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    • pp.689-695
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    • 2017
  • This study was carried out to investigate the physicochemical and adsorptive characteristics of black carbon (BC) materials for cesium in case of severe nuclear accidents. The BC was prepared with a xylem of oak and pine trees incompletely combusted with different ramp rate and final temperature. Carbon (C), hydrogen (H) and oxygen (O) atomic ratios, BET, pore structure, and zeta potential were characterized for the produced BC. A low cesium concentration ($C_w{\approx}10^{-7}M$) was used for sorption batch experiments. The H/C and O/C ratios of BC decreased with the increase of final temperature, which indicates a carbonization of the wood materials regardless of ramp rate and tree species. However, SEM images showed different pore structures depending on tree species such as steric and plate-like for oak-BC and pine-BC, respectively. The greatest sorption distribution coefficients of $K_{d,Cs}{\approx}1,200{\sim}1,800L\;kg^{-1}$ were observed for the oak-BC produced at $400^{\circ}C$, while comparatively low $K_{d,Cs}$ < $100L\;kg^{-1}$ for pine-BC. In addition, the sorption capabilities of BC declined with the increase of combustion temperature up to $600^{\circ}C$, because high temperature destroyed surface functionalities with the rise of ash components in the BC. Therefore, the sorption processes of BC for radioactive cesium are predominantly controlled by final production temperature of BC as well as raw materials (e.g., tree species).