• Title, Summary, Keyword: zirconium separation

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Synthesis and Phosphorus Adsorption Characteristics of Zirconium Magnetic Adsorbent Having Magnetic Separation Capability (자기분리가 가능한 지르코늄 자성 흡착제의 합성과 인 흡착 특성)

  • Lim, Dae-Seok;Kim, Yeon-Hyung;Kim, Dong-Rak;Lee, Tae-Gu;Lim, Hak-Sang
    • Journal of Korean Society of Water and Wastewater
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    • v.26 no.3
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    • pp.431-442
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    • 2012
  • The purpose of this study, is to separate magnetic separation devices using permanent magnets by using magnetization characteristics remaining in treated water after adsorption and synthesizing phosphorus adsorbent capable of magnetic separation for efficient removal of phosphorus. The synthesis of the adsorbent which set Zirconium(Zr) having high friendly features for phosphorus as an element, and by synthesizing Iron Oxide($Fe_3O_4$, another name of $Fe_3O_4$ is magnetite) being able to grant magnetism to Zirconium Sulfate($Zr(SO_4)_2$), zirconium magnetic adsorbent(ZM) were manufactured. In order to consider the phosphorus adsorption characteristics of adsorbent ZM, batch adsorption experiment was performed, and based on the results, pH effect, adsorption isotherm, adsorption kinetics, and magnetic separation have been explore. As the experiment result, adsorbent ZM showed a tendency that the adsorption number was decreased rapidly at pH 13; however, it was showed a high amount of phosphorus removal in other range and it showed the highest amount of phosphorus removal in pH 6 of neutral range. In addtion, the Langmuir adsorption isotherm model is matched well, and D-R adsorption isotherm model is ranged 14.43kJ/mol indicating ion exchange mechanism. The result shown adsorption kinetics match well to the Pseudo-second-order kinetic model. The adsorbent ZM's capablility of regenerating NaOH and $H_2SO_4$, was high selectivity on the phosphorus without impacts on the other anions. The results of applying the treated water after adsorption of phosphorus to the magnetic separation device by using permanent magnets, shows that capture of the adsorbent by the magnetization filter was perfect. And they show the possibility of utilization on the phosphorus removal in water.

Column Chromatographic Separation of Titanium, Zirconium and Niobium (Ti, Zr 및 Nb의 원통크로마토그라프 분리)

  • Chul Lee;Yung Chang Yim;Koo Soon Chung
    • Journal of the Korean Chemical Society
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    • v.17 no.1
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    • pp.15-19
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    • 1973
  • A method was developed for the separation of titanium, niobium and zirconium together in a group from the coexisting ions of various metals such as iron, cobalt, nickel, yttrium and rare earths by means of the cation exchange column using ${\alpha}$-hydroxyisobutyric acid as the eluent. In the course of the present investigation, it was found that the tailing phenomena of zirconium were attributable to the hydroxide precipitation which was made prior to the elution. For example, if zirconium was precipitated by sodium hydroxide, the tailing of zirconium became very serious in contrast to the results reported by others. This paper describes how these tailing phenomena of zirconium were prevented and how a practical procedure for the separation of these ions was, achieved using ion-exchange method. Using the present method the nuclides of $^{90m}Y$ and $^{90}Y$ were separated with radiochemical purity from the irradiated zirconium.

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Study on the Preparation of Inorganic Composite Membrane and Characteristics of Gas Separation of Zirconium Modified Polycarbosilane via Pyrolysis (지르코늄 혼성 폴리카르보실란의 열분해에 의한 무기 복합막 제조 및 기체분리 특성 연구)

  • Kang, Phil Hyun;Lee, Kew Ho;Yang, Hyun Soo
    • Applied Chemistry for Engineering
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    • v.10 no.8
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    • pp.1099-1103
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    • 1999
  • The surface of an ${\alpha}$-alumina tube was coated with zirconium modified polycarbosilane(PZC) by dip-coating method. Then the tube was pyrolyzed at 573~823 K. The prepared inorganic composite membrane was in $1{\mu}m$ thickness and had no pinholes larger than several nm. For the pyrolyzed inorganic composite membrane, the permeation test of He, $N_2$, $CO_2$, and $O_2$ was performed at 303~423 K. The gas permeation and separation factor were increased with increasing permeation temperature. The permeation for gases was controlled by the activated diffusion mechanism. The separation factor of $CO_2$, to $N_2$was 4.9 at 363 K on the composite membrane pyrolyzed at 823 K and its value was higher than that of He and $O_2$.

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Mutual Separation of Am and Eu by Solvent Extraction with di-(2-ethylhexyl)phosphoric acid Containing Zirconium(III) (Zr을 함유한 di-(2-ethylhexyl)phosphoric acid에 의한 Am과 Eu의 상호분리(III))

  • Yang, Han-Beom;Lee, Eil-Hee;Lim, Jae-Gwan;Kim, Jong-Gu;Kim, Jung-Suk;Yoo, Jae-Hyung
    • Applied Chemistry for Engineering
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    • v.8 no.6
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    • pp.1006-1013
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    • 1997
  • This study was carried out to elucidate the chemical characteristics of mutual separation for Am and Eu, which were selected as a stand-in from minor actinide and rare earth elements, by solvent extraction with di-(2-ethylhexyl)phosphoric acid containing zirconium at batch system. As results, 92.3% of Am and 99.1% of Eu were coextracted with 1M DEHPA/n-dodecane containing zirconium (Zr $concentration=8.7g/{\ell}$) at 0.5M $HNO_3$ in the extraction step. The extraction yields of Am and Eu were proportionally increased with the concentration of Zr in Zr salt of 1M DEHPA/n-dodecane having the synergistic effect. In the lst stripping step for the selective separation of Am, 38.1% of Am and 3% of Eu were stripped with the mixed solution of 0.05M DTPA and 1M lactic acid adjusted pH of 3.0. At that time, the separation factor calculated from the distribution coefficients of Am and Eu was 14.2. In the 2nd Stipping step to remove the Eu remained the organic phase after the lst stripping step, 94.4% 0f Eu was stripped into aqueous phase with 6M $HNO_3$.

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Stability of Zirconium Metal Organic Frameworks with 9,10- Dicarboxylic Acid Anthracene as Ligand

  • Xiao, Sheng-Bao;Chen, Sai-Sai;Liu, Jin;Li, Zhen;Zhang, Feng-Jun;Wang, Xian-Biao;Oh, Won-Chun
    • Journal of the Korean Ceramic Society
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    • v.53 no.2
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    • pp.200-205
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    • 2016
  • With high specific surface area and pore structural diversity, MOFs show important applications in gas storage, catalysis, sensing, separation, and biomedicine. However, the stability of the structure of MOFs has restricted their application and development. In this study, zirconium metal organic frameworks with 9,10-dicarboxylic acid anthracene as ligand, named UIO-66 ($H_2DCA$), were synthesized and their properties and structures were characterized by XRD, SEM, and $N_2$ adsorption. We focus on the stability of the structure of UIO-66 ($H_2DCA$) under different conditions (acid, alkali, and water). The structural changes or ruins of UIO-66 ($H_2DCA$) were traced by means of XRD, TG, and FT-IR under different conditions. The results show that the UIO-66 ($H_2DCA$) materials are stable at 583 K, and that this structural stability is greatly influenced by different types of acid and alkali compounds. Importantly, we found that the structures maintain their stability in environments of nitric acid, triethylamine, and boiling water.

Radiochemical separation of 89Zr: a promising radiolabel for immuno-PET

  • Vyas, Chirag K.;Park, Jeong Hoon;Yang, Seung Dae
    • Journal of Radiopharmaceuticals and Molecular Probes
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    • v.2 no.1
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    • pp.43-50
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    • 2016
  • $^{89}Zr$ with the favorable nuclear decay kinetics and chemical properties is an appealing radiometal for its application in immuno-PET using radiolabeled monoclonal antibodies. Rising demand of ultrahigh purity and high-specific activity $^{89}Zr$ has propelled the radiochemist worldwide to develop an overall efficacious method for its promising separation from the target matrix $^{89}Y$. The requirement of elevated radiochemical purity (${\geq}$ 99.99%) has accelerated the efforts since last two decades to achieve higher decontamination and separation factors of carrier free $^{89}Zr$ over $^{89}Y$ using several suitable separation techniques. However, each of the technique has its own pros and cons which prior to its actual medical application needs to be optimized and thoroughly scrutinized to avoid further complications during radiolabelling of the pharmaceuticals. In this short review article we will specifically consider as well focus on the historical development and the recent advances on the radiochemical separation of $^{89}Zr$ from $^{89}Y$ which will be helpful for the separation scientist involved in this area to understand the existing available means and plan the strategy to investigate and develop the novel techniques to overcome the problems involved in the present methods.

Paper Electrophoretic Separation of Fission Products (여과지 전기영동에 의한 핵분열 생성물 분리)

  • Byung Hun Lee;Jong Du Lee;Young Kuk Kim
    • Nuclear Engineering and Technology
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    • v.13 no.4
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    • pp.254-263
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    • 1981
  • Paper electrophoretic separation of fission products has been carried out by using the specially designed migration apparatus. In general, the isolation of rubidium, strontium, zirconium, ruthenium, cesium, cerium, molybdenum, and some short-lived fission products is more efficient under 0.1M HCl electrolyte as compared with 0.1M NaOH electrolyte. In addition to Np-239, 1-131∼135 were, in particular, observed with different iodine chemical species obtained by the paper-electrophoretic separation of short, neutron-irradiated uranyl nitrate solution.

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Separation and Purification for the Determination of Zirconium and Its Isotopes in PWR Spent Nuclear Fuels (PWR 사용후핵연료 중 Zr 및 Zr 동위원소 정량을 위한 분리 및 정제)

  • Kim, Jung Suk;Jeon, Young Shin;Park, Yong Joon;Lee, Chang Heon;Kim, Won Ho
    • Analytical Science and Technology
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    • v.11 no.6
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    • pp.421-428
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    • 1998
  • A method has been studied to separate Zr from various fission products in PWR spent nuclear fuels. A solution containing metal ions in place of radioactive fission products was prepared. The Zr was separated with 5 M HCl followed by eluting metal ions such as Ce, Nd, Cs, Rb, Ba, Sr, Ru, Rh, Pd, Ag and Cd with 12 M HCl on Dowex $1{\times}8$, anion exchange resin. The recovery of Zr was more than 95%. The purification of Zr was carried out on anion exchange resin, Dowex $1{\times}8$, in 5 M HCl in order to remove Mo causing isobaric effect during mass spectrometry. The method was applied to separate Zr from a spent PWR fuel. From mass spectrometric measurement, the purified Zr portion was not showed the isobars from other elements such as Mo and Sr.

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A Study on the Separation of Long-lived Radionuclides and Rare Earth Elements by a Reductive Extraction Process (환원추출에 의한 장수명핵종과 희토류 원소의 분리 연구)

  • 권상운;안병길;김응호;유재형
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.421-425
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    • 2003
  • The reductive extraction process is an important step to refine the TRU product from the electrorefining process for the preparation of transmutation reactor fuel. In this study, it was studied on the reductive extraction between the eutectic salt and Bi metal phases. The solutes were zirconium and the rare earth elements, where zirconium was used as a surrogate for the transuranic(TRU) elements. All the experiments were performed in a glove box filled with a argon gas. Li-Bi alloy was used as a reducing agent to reduce the high chemical activity of Li. The reductive extraction characteristics were examined using ICP, XRD and EPMA analysis. The reduction reaction was equilibrated within 3 hours after the Li addition. Three eutectic salt systems were compared and Zr was successfully separated from the rare earth elements in all the three salt systems.

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