• Title/Summary/Keyword: uranium ion

검색결과 94건 처리시간 0.091초

고밀집 Glassy Carbon 섬유 다발체 전극 전해계를 이용한 금속 이온의 in-situ 전해 역추출 특성 연구 (A Study on in-situ Electrolytic Stripping of a Metal Ion by Using a Highly Packed Glassy Carbon Fiber Column Electrode System)

  • 김광욱;김영환;이일희;유재형
    • 공업화학
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    • 제9권4호
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    • pp.475-480
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    • 1998
  • 본 연구에서는 고밀집 glassy carbon (GC) 섬유 다발체 전극 전해계를 사용하여 우라늄 (VI)를 함유한 유기상과 질산 수용상의 혼합상에서 전해 역추출시 우라늄 (VI) 환원 전해특성 연구가 수행되었고, 이에 관한 전해 역추출 모델을 제시하였다 우라늄 (VI) 전해환원 반응은 혼합상 내의 수용상에서 보다 혼합상 내의 유기상에서 빨리 일어났다. 유기상의 유속이 증가하는 경우 역추출 과정에서 유기상 내 우라늄 이온의 확산 저항 증가에 의해서 수용상으로의 역추출은 증가하다 일정하게 되었으며, 수용상 유속 변화는 총 우라늄 (VI) 환원전류에는 영향을 주지 않았다. 전해반응이 없는 경우보다 전해 반응이 동반되는 경우 우라늄 역추출이 보다 효과적으로 이루어 짐을 알 수 있었다.

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방사선 중합에 의한 ACF/PP-g-AN 복합섬유의 합성 및 우라늄 분리에 관한 연구 (A Study on the Synthesis of ACE/PP-g-AN Hybrid Fibers by Irradiation and Separation of Uranium)

  • 황택성;황대성;노영창
    • 폴리머
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    • 제24권2호
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    • pp.174-181
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    • 2000
  • 방사선 전조사법을 이용하여 아크릴로니트릴을 ACF/PP 복합섬유에 그라프트 반응시켜 섬유형 ACF/PP-g-AN 공중합체를 합성하였다. 합성한 공중합체의 FT-lR 결과 2250$cm^{-1}$ / 부근에서 -C=N에 대한 피크, 3450$cm^{-1}$ / 부근에서 -OH와 -NH$_2$에 의한 피크 확인으로 그라프트 반응 및 아미드옥심화 반응을 확인할 수 있었다. 아미드옥심화된 ACF/PP-g-AN 공중합체의 우라늄 이온에 대한 흡착능의 최적시간은 8일이었으며, 최적 pH는 8이었다. 동일 조건하에서의 흡착능은 아미드옥심기의 함량이 증가할수록, 그라프트율이 116.3%일 때 최대 흡착능을 나타내었다. 또한 ACF/PP-g-AN 공중합체는 10회 이상 흡착능의 변화없이 흡탈착이 가능한 홉착제임을 알 수 있었다.

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Adsorption of Rare Earth Metal Ion on N-Phenylaza-15-Crown-5 Synthetic Resin with Styrene Hazardous Material

  • Kim, Se-Bong;Kim, Joon-Tae
    • 통합자연과학논문집
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    • 제7권2호
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    • pp.130-137
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    • 2014
  • Resins were synthesized by mixing N-phenylaza-15-crown-5 macrocyclic ligand attached to styrene (2th petroleum in 4th class hazardous materials) divinylbenzene (DVB) copolymer with crosslink of 1%, 2%, 6%, and 12% by substitution reaction. The synthesis of these resins was confirmed by content of chlorine, element analysis, thermo gravimetric analysis (TGA), surface area, and IR-spectroscopy. The effects of pH, equilibrium arrival time, dielectric constant of solvent and crosslink on adsorption of metal ions by the synthetic resin adsorbent were investigated. The metal ions were showed fast adsorption on the resins above pH 4. The optimum equilibrium time for adsorption of metallic ions was about two hours. The adsorption selectivity determined in ethanol was in increasing order uranium (VI) > zinc (II) > europium (III) ions. The uranium ion adsorbed in the order of 1%, 2%, 6%, and 12% crosslink resin and adsorption of resin decreased in proportion to the order of dielectric constant of solvents.

Extraction Behavior of Uranyl Ion From Nitric Acid Medium by TBP Extractant in Ionic Liquid

  • Kim, Ik-Soo;Chung, Dong-Yong;Lee, Keun-Young
    • 방사성폐기물학회지
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    • 제18권4호
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    • pp.457-464
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    • 2020
  • In this study, extraction of uranium(VI) from an aqueous nitric acid solution was investigated using tri-n-butyl phosphate (TBP) as an extractant in an ionic liquid, 1-alkyl-3-methylimidazolium bis (trifluoromethylsulfonyl)imide ([Cnmim][Tf2N]). The distribution ratio of U(VI) in 1.1 M TBP/[Cnmim][Tf2N] was significantly high when the concentration of nitric acid was low. The value of the distribution ratio decreased as the concentration of the nitric acid increased at lower acidities, and then increased with a nitric acid concentration of up to 8 M. This can be attributed to the different extraction mechanisms of U(VI) based on nitric acid concentrations. Thus, a cation exchange at low acidity levels and an ion-pair extraction at high acidity levels were suggested as the extraction mechanism of U(VI) in the TBP/[Cnmim][Tf2N] system.

Separation and purification of elements from alkaline and carbonate nuclear waste solutions

  • Alexander V. Boyarintsev ;Sergei I. Stepanov ;Galina V. Kostikova ;Valeriy I. Zhilov;Alfiya M. Safiulina ;Aslan Yu Tsivadze
    • Nuclear Engineering and Technology
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    • 제55권2호
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    • pp.391-407
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    • 2023
  • This article provides a survey of wet (aqueous) methods for recovery, separation, and purification of uranium from fission products in carbonate solutions during the reprocessing of spent nuclear fuel and methods for removal of radionuclides from alkaline radioactive waste. The main methods such as selective direct precipitation, ion exchange, and solvent extraction are considered. These methods were compared and evaluated for reprocessing of spent nuclear fuel in carbonate media according to novel alternative non-acidic methods and for treatment processes of alkaline radioactive waste.

양이온 교환능을 갖는 K-Birnessite 콜로이드에 의한 수용성 우라늄(VI) 이온의 흡착 연구 (Sorption of aqueous uranium(VI) ion onto a cation-exchangeable K-birnessite colloid)

  • 강광철;김승수;백민훈;권수한;이석우
    • 분석과학
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    • 제23권6호
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    • pp.566-571
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    • 2010
  • 양이온 교환능력을 갖는 합성 K-birnessite를 이용하여 수용성 우라늄 이온($UO_2^{2+}$)에 대한 흡착 거동을 조사하였다. K-birnessite는 KMnO4 수용액과 염산을 반응시켜 합성하였으며, 합성된 K-birnessite의 구조, 비표면적 및 표면전하 등 물리화학적 특성을 규명하였다. $K^+$ 이온은 층상구조를 갖는 $MnO_2$ 층간에 존재하였으며, BET 비표면적은 $38.30\;m^2/g$이었다. 우라늄 흡착실험 조건인 pH 5.00, 이온세기 0.010M $NaClO_4$에서 측정된 K-birnessite의 표면전하는 $-1.65\;C/m^2$이었다. 우라늄 이온은 K-birnessite 층간의 $K^+$와 이온교환 반응을 통하여 흡착하였으며, 분배계수는 일반적인 이온교환물질과 유사하였다. 본 연구결과는 고준위 방사성 폐기물 지하처분장으로부터 유출될 수 있는 방사성물질의 이동을 저지하는 방법으로 활용될 수 있을 것이다.

하이드록실 아민으로 처리한 아크릴 섬유의 우라늄 흡착특성 (Adsorption Properties of Uranium on Acrylic Fibers Treated with Hydroxylamine)

  • 진영길;이정숙
    • 한국의류학회지
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    • 제14권2호
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    • pp.98-103
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    • 1990
  • Fibrous adsorbents containing amidoxime group which make chelate complexes with uranyl ions are studied for the recovery of uranium from sea water. Acrylic fibers are used as base Polymer. The adsorption properties of uranium are carried out to examine pH effect, concen-tration dependence, adsorption rate, separation, and chelate complex. The results obtained are as follows; 1. Metal capacity of U (VI) ion is in the range of pH $2\~10.2$. Amidoxime group-containing fiber recover U (VI) ions existed in sea water or waste water in extremely small quantities. 3. Using amidoxime group-containing fiber Cu (II) and U (VI) are separated with each other in dilute nitric acid solution (pH 2.3). 4. U (VI) chelate complexes are conformed by tridendate ligands, which are coordinated with one nitrogen and two oxygens onto amidoxime group-containing fiber.

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질소-주게 합성수지를 이용한 U(VI), Cu(II), Dy(III) 이온들의 흡착특성 (Adsorption Characteristic of U(VI), Cu(II), Dy(III) Ions Utilizing Nitrogen-Donator Synthetic Resin)

  • 노기환;김준태;김희정
    • 환경위생공학
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    • 제21권3호
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    • pp.52-60
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    • 2006
  • The ion exchange resins have been synthesized from chlormethyl styrene-1,4-divinylbenzene(DVB) with 1%, 2%, and 20%-crosslinking and macrocyclic ligand of cryptand 21 by copolymerization method and the adsorption characteristics of uranium(VI), copper(II) and dysprosium(III) metallic ions have been investigated in various experimental conditions. The synthesis of these resins was confirmed by content of chlorine, element analysis, and IR-spectrum. The effects of pH, equilibrium time, dielectric constant of solvent and crosslink on adsorption of metallic ions were investigated. The metal ion was showed fast adsorption on the resins above pH 3. The optimum equilibrium time for adsorption of metallic ions was about two hours. The adsorption selectivity determined in ethanol was in increasing order uranium$(UO^{2+}_2)\;>\;copper(Cu^{2+})\;>\;dysprosium(Dy^{3+})$ ion. The adsorption was in order of 1%, 2%, and 20% crosslink resin and adsorption of resin decreased in proportion to order of dielectric constant of solvents.

레이저 유발형광법을 이용한 우라늄 작업자의 뇨 형광 분석 (An Improved Laser-Induced Fluorimetry for Assay of Uranium in Urine)

  • Lee, Sang-Mok;Shin, Jang-Soo;Kim, Cheol-Jung
    • Nuclear Engineering and Technology
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    • 제25권2호
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    • pp.255-258
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    • 1993
  • 펄스형 질소레이저를 사용한 time-resolved laser-induced fluorimetry를 이용하여 우라늄 작업자의 뇨속에 함유되어 있는 우라늄의 농도를 간단한 전처리만으로 정량분석하는 방법을 연구하였다. 형광분석할 때에 뇨에 함유된 chloride ion은 우라늄 형광을 심하게 quenching하는 것으로 알려져 있으며, 따라서 이를 제거하기 위한 전처리 과정에서 많은 시간 소모와 큰 실험 오차를 유발하고 있다. 본 방법에서는 10% Fluran 수용액을 뇨에 첨가하여 뇨함량이 약 1% 정도가 되었을 때 뇨속의 chloride에 의한 quenching 영향을 최소한으로 줄일 수 있었으며, 시간 0에서의 형광강도를 계산하여 형광강도의 농도에 대한 직선성을 측정한 결과 우라늄 농도 범위 10-500 ppb에서 우수한 직선성을 나타내었다.

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Feasibility Study of Isotope Ratio Analysis of Individual Uranium-Plutonium Mixed Oxide Particles with SIMS and ICP-MS

  • Esaka, Fumitaka;Magara, Masaaki;Suzuki, Daisuke;Miyamoto, Yutaka;Lee, Chi-Gyu;Kimura, Takaumi
    • Mass Spectrometry Letters
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    • 제2권4호
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    • pp.80-83
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    • 2011
  • Isotope ratio analysis of nuclear materials in individual particles is of great importance for nuclear safeguards. Although secondary ion mass spectrometry (SIMS) and thermal ionization mass spectrometry (TIMS) are utilized for the analysis of individual uranium particles, few studies were conducted for the analysis of individual uranium-plutonium mixed oxide particles. In this study, we applied SIMS and inductively coupled plasma mass spectrometry (ICP-MS) to the isotope ratio analysis of individual U-Pu mixed oxide particles. In the analysis of individual U-Pu particles prepared from mixed solution of uranium and plutonium standard reference materials, accurate $^{235}U/^{238}U$, $^{240}Pu/^{239}Pu$ and $^{242}Pu/^{239}Pu$ isotope ratios were obtained with both methods. However, accurate analysis of $^{241}Pu/^{239}Pu$ isotope ratio was impossible, due to the interference of the $^{241}Am$ peak to the $^{241}Pu$ peak. In addition, it was indicated that the interference of the $^{238}UH$ peak to the $^{239}Pu$ peak has a possibility to prevent accurate analysis of plutonium isotope ratios. These problems would be avoided by a combination of ICP-MS and chemical separation of uranium, plutonium and americium in individual U-Pu particles.