• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.9 no.3
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• pp.131-139
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• 2011

This study was carried out to examine the stability of $Na_2CO_3-H_2O_2$ carbonate solution with aging time in the dissolving solution after oxidative dissolution of U by a carbonate solution, the Cs/Re filtrate after selective precipitation of Cs and Re (as a surrogate for Tc), and the acidification filtrate after precipitation of U by acidification, respectively. The compositions of dissolving solution were not changed with ageing time, and the selective precipitation of Re and Cs was also not affected without regard to the aging time of dissolving solution. The successive removal of Cs and Re from a carbonate dissolving solution was possible. However, the recovery yield of U by acidification was decreased with increasing the aging time of the dissolving solution and the Cs/Re-filtrate, respectively, because U was converted from the uranyl peroxocarbonato complex to the uranyltricarbonate in the solution aged for a long time. Accordingly, it is effective that a dissolving solution and a Cs/Re filtrate are treated within the aging of 7 days, respectively, in order to recover U more than 99%. On the other hand, the recovery of U was carried out in order of the oxidative dissolution of U selective precipitation of Re and Cs precipitation of U by acidification. Almost all of U and a part of FP were co-dissolved in oxidative dissolution step. Over 99% of Re and Cs from the FP co-dissolved with U could be removed by a TPPCl (tetraphenylphosphonium chloride) and a NaTPB (sodium tetraphenylborate), respectively. U was precipitated nearly 100% by acidification to pH 4. Therefore, it was confirmed that the validity of recovery of U by precipitation methods from a SF (spent fuel) in the $Na_2CO_3-H_2O_2$ solution.

• Ecology and Resilient Infrastructure
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• v.3 no.4
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• pp.279-284
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• 2016

Mine tailings generated during mining activity often contain high concentrations of heavy metals, with pyrite-containing mine tailings in particular being a major cause of environmental problems in mining areas. Chemical cell technology, or fuel cell technology, can be applied to leach heavy metals in pyrite-containing mine tailings. As pyrite dissolves through spontaneous oxidation (i.e. galvanic oxidation) in the anode compartment of the cell, $Fe^{3+}$, sulfuric acid are generated. A decrease in pH due to the generation of sulfuric acid allows heavy metals to be leached from pyrite-containing mine tailings. In this study, pyrite was dissolved for 4 weeks at $23^{\circ}C$ in an acidic solution (pH 2) and in a galvanic reactor, which induces galvanic oxidation, and total Fe leached from pyrite and pH were compared in order to investigate if galvanic oxidation can facilitate pyrite oxidation. The change in the pyrite surface was analyzed using a scanning electron microscope (SEM). Comparing the total Fe leached from the pyrite, there were 2.9 times more dissolution of pyrite in the galvanic reactor than in the acidic solution, and thus pH was lower in the galvanic reactor than in the acidic solution. Through SEM analysis of the pyrite that reacted in the galvanic reactor, linear-shaped cracks were observed on the surface of the pyrite. The study results show that pyrite dissolution was facilitated through the galvanic oxidation in the galvanic reactor, and also implied that the galvanic oxidation can be one remediation option for pyrite-containing mine tailings.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2009.05a
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• pp.237-238
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• 2009

1999년 Zwilling 등은 타이타늄과 타이타늄 합금위에 불산을 포함하는 산성 전해질에서 양극산화 방법에 의해 $TiO_2$ 나노튜브를 형성시켰다. 그러나 HF의 강한 용해성으로 인해 튜브의 길이를 500 nm이상 성장 시킬 수 없다는 문제점을 가지고 있었고 그 후에 HF대신에 전해질에 $NH_{4}F$를 혼합하여 pH를 조절하는 방법으로 $TiO_2$가 용해되는 속도를 감소시켜 약 $2{\sim}4$배 더 크게 성장 시킬 수 있다고 보고한 바 있지만 수 ${\mu}m$ 이상의 길이로는 성장 시킬 수 없다는 한계를 가지고 있었다. 최근에는 불소이온을 포함하는 점액질의 유기전해질에서 높은 종횡비, 40-60 nm의 작은 기공직경과 매끄러운 튜브벽을 가지는 수 um이상의 나노튜브를 성장 시키는 보고가 있으나 $TiO_2$ 나노튜브의 제조에 영향을 미치는 파라메타에 대한 연구가 아직 많지 않은 실정이다. 따라서 본 연구에서는 전해질의 구성, 전압, 양극산화 시 교반의 영향에 대해 조사하였다. 불산과 에틸렌글리콜 전해질에서 형성된 $TiO_2$ 나노튜브의 비 표면적의 차이를 조사했고 튜브의 길이와 기공크기도 양극산화 시 인가전압과 전해질 구성에 따라 다른 것을 확인할 수 있었다. 이는 포어 바닥에서 국부적인 산성화를 유발하는 타이타늄의 가수분해와 $TiO_2$의 용해는 산화피막층의 용해작용을 증가시키는 수소이온의 농도를 증가시고 그에 따라 인가접압이 증가함에 따라 전해질 내의 이온수송을 활발하게 하기 위한 구동력이 증가해 전류밀도가 높아지는 것으로 확인되었단. 또한 양극산화 동안 전해질을 교반 한 경우 그런지 않은 경우에 비해 전해질 내의 유속(mass flow)를 증가시켜 더 긴 나노튜브를 얻을 수 있었다.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2004.04a
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• pp.396-399
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• 2004

산화환경에 노출된 폐광석에 포함되어 있는 황화광물은 산소와 물과의 화학반응을 통해 산화작용을 받게 되고, 이로 인하여 Fe, Mn, Pb, Zn, Cu 및 As등의 원소의 용해반응이 발생할 것으로 예상된다. 그러나 이와 같이 용해된 금속이온은 pH등 환경의 변화에 따라 2차광물(산화광물 및 황산염광물)로 침전되거나 흡착되어 수용액으로부터 제거되어 자연적으로 고정화 될 수 있다. 이처럼 황화광물의 산화작용에 의해 형성된 2차광물에 대한 광물학적 연구는 광산복원을 결정하는데 직접적인 지구화학적 자료로 활용될 수 있다. 삼산제일광산에 방치된 폐광석을 대상으로 XRD, SEM/EDS을 이용하여 광물학적 연구를 수행한 결과 침전과 공침, 흡착 등의 화학반응을 통하여 현재 고정화되고 있는 것이 확인되었다.

• Korean Journal of Food Science and Technology
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• v.21 no.5
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• pp.706-709
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• 1989

Ascorbic acid was solubilized in perilla oil via reversed micelle using small amount of water and lecithin as surfactant. The effect of the solubilized ascorbic acid on the oxidative stability of perilla oil was investigated. The autoxidation of the oil was greatly retarded with the solubilized ascorbic acid compared to the synthetic antioxidants employed. However, the combination with ${\delta}-tocopherol$ did not show any significant synergism.

• Korean Journal of Food Science and Technology
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• v.32 no.6
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• pp.1227-1233
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• 2000

Lycopene was subjected to ozonolysis in ice-cold dichloromethane. The ozonolysis products were fractionated with a silica column and the carbonyl fraction was analyzed by ODS-HPLC with a photodiode array detector and by LC-MS. UV-vis spectra and $[M+H]^+$ of the carbonyl compound peaks showed clearly that acycloretinal, apo-14'-lycopenal, apo-12'-lycopenal, apo-10'-lycopenal, apo-8'-lycopenal and apo-6'-lycopenal were formed by ozonolysis of lycopene. Lycopene was solubilized in toluene and aqueous Tween 40, and then oxidized by incubating at $37^{\circ}C$ under atmospheric oxygen. Carbonyl compounds were produced. In comparison with autoxidation and ozonolysis, each compound showed the same retention time and UV-vis spectra are identical to the reference cleavage products prepared by ozonolysis of lycopene. Thus, eccentric cleavage of lycopene was confirmed to occur in vitro under oxidation condition.

• 한국전기화학회:학술대회논문집
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• 2003.04a
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• pp.42-42
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• 2003

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.443-444
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• 2016

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.2
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• pp.85-93
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• 2013

This study has been carried out to elucidate the characteristics of the dissolution for Thermal Decomposed Solid Waste of uranium-bearing sludge (TDSW), the removal of impurities by an alkalization in a nitric acid dissolving solution of TDSW, and the selective removal (/recovery) of uranium by an acidification in an carbonate alkali solution, respectively. TDSW generated by thermal decomposition of U-bearing sludge which was produced in the uranium conversion plant operation, was stored in KAERI as a solid-powder type. It is found that the dissolution of TDSW is more effective in nitric acid dissolution than oxidative-dissolution with carbonate. At 1 M nitric acid solution, TDSW was undissolved about 30wt% as a solid residue, and uranium contained in TDSW was dissolved more than 99%. In order to the alkalization for the nitric acid dissolving solution of TDSW, carbonate alkalization is more effective with respect to remove the impurities. At the carbonate alkali solution controlled to about 9 of pH, Al, Ca, Fe and Zn co-dissolved with U in dissolution step was removed about $98{\pm}1%$. On the other hand, U could be recovered more than 99% by an acidification at pH about 3 in a carbonate alkali solution, which was nearly removed the impurities, adding 0.5M $H_2O_2$. It was found that uranium could be selectively recovered (/removed) from TDSW.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.330-331
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• 2009