• 한국세라믹학회지
• /
• 제26권4호
• /
• pp.521-531
• /
• 1989

The dependence of the chemical durability of simulated waste glasses containing the simplified waste similar to the SRP waste on compositions of host glasses, amounts of waste loading, and kinds of leachants has been investigated as a basic study on the waste immobilization through vitrification. The maximum limit of the amount of waste loading for glassforming with the host sodium borosilicate glasses selected in this study was 50wt%. The chemical durability of waste glasses whose host glass belonged to the immiscible composition region was much higher than that of waste glasses whose host glass belonged to the miscible composition region. The former waste glass showed lower chemical durability in deionized and silicate waters than in brine, while the latter glass showed the lowest chemical durability in deionized and silicate waters than in brine, while the latter glass showed the lowest chemical durability in silicate water. It was also observed that the total leaching rates in brine were noticeably small in comparison with those in other solutions. The composition of the host borosilicate glass which was suitable for the treatment of the waste through vitrification was found to be 25 Na2O-5B2O3-70SiO2(wt.%).

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2005년도 Proceedings of The 6th korea-china joint workshop on nuclear waste management
• /
• pp.51-59
• /
• 2005

The long-lived fission product $^{99}Tc$ is present in large quantities in nuclear wastes and its chemical behavior in aqueous solution is of considerable interest. Under oxidizing conditions technetium exists as the anionic species $TcO_4^-$ whereas under the reducing conditions it is generally predicted that technetium will be present as $TcO_2{\cdot}nH_2O$. Technetium oxide was prepared by reduction of a technetate solution with $Sn^{2+}$. The concentration of total technetium and Tc(IV) species in the solutions were periodically determined by separating the oxidized and reduced technetium species using a solvent extraction procedure and counting the beta activity of the $^{99}Tc$ with a liquid scintillation counter. The experimental results show that the rate of oxidation of Tc(IV) in simulated groundwater and redistilled water is about $(1.49{\~}1.86){\times}10^{-9} mol/(L{\cdot}d$) under aerobic conditions, but Tc(IV) in simulated groundwater and redistilled water is not oxidized under anaerobic conditions. Under aerobic or anaerobic conditions the solubility of Tc(IV) oxide in simulated groundwater and redistilled water is equal on the whole.

• Nuclear Engineering and Technology
• /
• 제44권8호
• /
• pp.939-944
• /
• 2012

Deposition potential, deposition time, square wave frequency, rotation speed of the rotating disc electrode, and palladium concentration were studied on a Glassy Carbon Electrode (GCE) in 0.01M HCl for the determination of palladium in High Level Nuclear Waste (HLNW) by anodic stripping voltammetry. Experimental conditions were optimized for the determination of palladium at two different, $10^{-8}$ and $10^{-7}M$, levels. Error and standard deviation of this method were under 1% for all palladium standard solutions. The developed technique was successfully applied as a subsidiary method for the determination of palladium in simulated high level nuclear waste with very good precision and high accuracy (under 1 % error and standard deviation).

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
• /
• pp.245-256
• /
• 2004

The extraction of three kinds of amido podands, N,N,N'N'-tetrabutyl-3-oxa-pentanedi- amide (TBDGA), N,N,N'N'-tetra-isobutyl-3-oxa-pentanediamide(TiBDGA) and N,N,N'N'-tetra- butyl-3,6-dioxa-oct-anediam- ide(TBDOODA) on U(VI),Pu(IV), Am(III), Eu(III) and other metal ions is studied in nitric acid solutions. 40%octanol-kerosene is chosen as diluents to eliminate third phase and emulsion. TBDGA and TiBDGA show extraction selectivity to An(III) and Ln(III) much higher than to U(VI) and Pu(IV). Fe, Ru and Mo is poorly extracted by the three kinds of amid podands in 2~3mol/L $HNO_3$ solutions. Aiming to eliminate interface crude when using simulated HLLW solution in the system of 0.2mol/L TBDGA/Octanol＋kerosene, acetohydroxyamic acid was adapted. Distribution ratio of zirconium was decreased when adding acetohydroxyamic acid in aqueous solution, and interface crude disappeared as mixing extractant with HLLW. The counter-current extraction test is carried out in a set of miniature mixer-settler, with 0.2mol/L TBDGA/ 40% octanol-kerosene as extractant to separate U(VI), Pu(IV), Am(III) and Eu(III) from simulated high level liquid waste(HLLW) solution. In battery A, lanthanides and actinides are coextracted into organic phase with the recovery of 99.98% for U(Ⅵ), >99.99% for Pu(IV), and >99.99% for Am(III) and Eu(III) respectively. In battery R1, 99.99% U, 86.2% Pu and a part of Am or Eu are stripped into aqueous phase by 0.2mol/L acetohydroxyamic acid (AHA) in 0.01mol/L $HNO_3$ solution. In battery $R_2$, Am, Eu and remained Pu are completely back-extracted by 0.2mol/L AHA. This separation process contains no salt reagent, and it is not necessary to dilute HLLW feed.

• Nuclear Engineering and Technology
• /
• 제49권3호
• /
• pp.556-561
• /
• 2017

Serving as an excellent adsorbent and inorganic ion exchanger in the water purification field, zeolite 4A has in this work presented a strong capability for purifying radioactive waste, such as $Sr^{2+}$, $Cs^+$, and $Co^{2+}$ in water. During the processes of decontamination and decommissioning of suspended solids and organics in low-level radioactive wastewater, the purification performance of zeolite 4A has been studied. Under ambient temperature and neutral condition, zeolite 4A absorbed simulated radionuclides such as $Sr^{2+}$, $Cs^+$, and $Co^{2+}$ with an absorption rate of almost 90%. Additionally, in alkaline condition, the adsorption percentage even approached 98.7%. After conducting research on suspended solids and organics of zeolite 4A for the treatment of radionuclides, it was found that the suspended clay was conducive to absorption, whereas the absorption of organics in solution was determined by the species of radionuclides and organics. Therefore, zeolite 4A has considerable potential in the treatment of radioactive wastewater.

• 대한지하수환경학회지
• /
• 제3권2호
• /
• pp.51-59
• /
• 1996

지하 LPG 저장시설과 같은 지하수에 의존하는 시설물 인접지역에 폐기물매립장이 설치될 경우, 침출수 누출로 인한 지하수오염 예측 및 오염방지 대책수립이 요구되고, 이를 위한 지하수유동 및 용질 이동(Mass Transport) 해석을 실시하게 된다. 본 연구에서는 현재 U 지역 석유화학공단내에서 발생된 상기 와 같은 내용의 문제점을 해결하기 위하여 해석학적 해석 및 수치해석에 의한 침출수이동 예측을 실시하였으며 침출수제어 공법을 검토하였다. 해석학적 해석은 입력요소를 이송(Advenction)요인과 분산 (Dispersion)요인으로 구분하여, Peclet 수로 부터 각 요인의 침출수이동에 미치는 영향을 분석 검토하였으며, 보존성용질 이송확산 방정식으로부터 입력요소 변화율과 침출수이동속도 변화율의 관계를 함수식으로 도출하여, 입력요소 변화에 따른 침출수 이동속도 변화를 간단히 예측할 수 있었다. 수치해석은 지하수유동 및 용질이동 해석용 FEM 프로그램인 AQUA2D를 이용하여 침출수이동 예측을 위한 수치모의를 실시하였다. 침출수제어공법 검토를 위해서 3D 불연속체모형을 모의하고 모의된 모형을 대상으로 지하수유동해석을 실시하여 암반내 열극(Fracture)의 상호 연결성 분석을 통한 수벽(Water Curtain) 시스템의 타당성을 분석하였다. 해석학적 해석 및 수치모의 결과, 폐기물매립장으로 부터 지하 LPG 저장기지로 침출수가 30년 이내로 유입되는 것으로 예측되었으며, 이를 방지하기 위한 침출수 제어공법으로는 수직수벽 시스템이 효율적인 것으로 예측되었다.

• Environmental Engineering Research
• /
• 제23권1호
• /
• pp.92-98
• /
• 2018

Suitability of aluminium-based water treatment sludge (WTS), a waste product from water treatment facilities, was assessed for removal of heavy metals from an electroplating wastewater which had high concentrations of copper and chromium along with other heavy metals. Batch tests with simulated wastewater in single- and multi-metal solutions indicated the influence of initial pH and WTS dose on removal of six metals namely Cu(II), Co(II), Cr(VI), Hg(II), Pb(II) and Zn(II). In general, removal of cationic metals such as Pb(II), Cu(II) and Zn(II) increased with increase in pH while that of anionic Cr(VI) showed a reduction with increased pH values. Tests with multi-metal solution showed that the influence of competition was more pronounced at lower WTS dosages. Column test with diluted (100 times) real electroplating wastewater showed complete removal of copper up to 100 bed volumes while chromium removal ranged between 78-92%. Other metals which were present in lower concentrations were also effectively removed. Mass balance for copper and chromium showed that the WTS media had Cu(II) and Cr(VI) sorption capacities of about 1.7 and 3.5 mg/g of dried sludge, respectively. The study thus indicates that WTS has the potential to be used as a filtration/adsorption medium for removal of metals from metal-bearing wastewaters.

• Environmental Engineering Research
• /
• 제23권2호
• /
• pp.129-135
• /
• 2018

The aim of this study is to assess the applicability of ferrate(VI) in the efficient treatment of aqueous waste contaminated with potassium hydrogen phthalate (KHP) which is known to be a potent endocrine disrupting chemicals. Simulated batch reactor operations were conducted at a wide range of pH (7.0 to 12.0) and molar ratios of KHP to ferrate(VI). Kinetic studies were performed in the degradation process and overall rate constant was found to be 83.40 L/mol/min at pH 8.0. The stoichiometry of ferrate(VI) and KHP was found to be 1:1. Further, lower pH values and higher KHP concentrations were favoured greatly the degradation of KHP by ferrate(VI). Total organic carbon analysis showed that partial mineralization of KHP was achieved. The presence of several background electrolytes were studied in the degradation of KHP by ferrate(VI).

• 분석과학
• /
• 제13권6호
• /
• pp.699-704
• /
• 2000

도금폐수중의 시안이온의 전기화학적 분해 및 아연이온의 제거에 관한 연구를 백금으로 도금된 티타늄 양극과 스텐레스 음극 전극을 사용하여 수행하였다. 전기분해시간, 셀전류, 첨가제, 염화물농도등의 여러 가지 실험파라메터를 연구하여 도금폐수중의 시안화물 분해 및 수용액중의 아연이온의 효과적인 제거에 사용하였다. 셀전류와 첨가제의 종류에 따라 시안이온의 분해 및 아연이온의 제거 효율이 크게 영향을 받는 것이 발견되었다. 시안이온의 분해 및 아연이온의 제거를 위한 경제적이며 높은 효율을 나타내는 최적화된 조건은 1시간의 전기분해시간, 12A의 전류, 그리고 0.5 M NaCl 첨가제를 사용하여 확립하였다. 양극에서의 시안이온의 분해에 관한 반응메카니즘도 논의하였다.

• 한국광물학회지
• /
• 제21권4호
• /
• pp.341-347
• /
• 2008

포항지역 널리 분포하고 있는 규질이암으로부터 상업화를 위한 50리터 bench scale 수열장치를 사용하여 Na-A형 제올라이트의 합성을 성공적으로 수행하였고 또한 이 제올라이트를 이용하여 환경 개선재로 활용하는 연구를 수행하였다. 초기물질로 사용된 규질이암은 제올라이트의 주요 성분인 $SiO_2$ 및 $Al_2O_3$가 각각 70.7% 및 10.0% 함유되어 제올라이트의 합성에 유리한 조성을 가지고 있다. 이전의 실험실적 규모에서 수행된 동일한 조건인 $Na_2O/SiO_2\;=\;0.6$, $SiO_2/Al_2O_3\;=\;2.0$, $H_2O/Na_2O\;=\;98.6$의 조성비로 $80^{\circ}C$에서 18시간 동안 합성한 결과, Na-A형 제올라이트의 결정도 및 결정형태는 실험실적 규모와 유사하였고, 회수율 및 양이온 교환능은 각각 95% 및 215 cmol/kg으로 실험실적 규모에서 보다 약간 우수한 결과를 나타냈다. 합성된 Na-A형 제올라이트를 이용하여 모사폐액(Pb, Cd, Cu, Zn 및 Mn)에 중금속 제거율을 조사한 결과, 중금속 제거율은 Pb > Cd > Cu = Zn > Mn의 순서이었다. Mn을 제외한 다른 중금속들은 1500 mg/L에서 99% 이상의 제거율을 보였고, Mn의 경우도 98%의 제거율을 보여 합성된 Na-A형 제올라이트는 중금속 흡착제로서 우수한 특성을 나타냈다.