• Title/Summary/Keyword: Spent ion-exchange resin

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Separation of Vanadium and Tungsten from Simulated Leach Solutions using Anion Exchange Resins (음이온교환 수지를 이용한 바나듐/텅스텐 혼합용액으로부터 바나듐/텅스텐 분리회수에 관한 연구)

  • Jong Hyuk Jeon;Hong In Kim;Jin Young Lee;Rajesh Kumar Jyothi
    • Resources Recycling
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    • v.31 no.6
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    • pp.25-35
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    • 2022
  • The adsorption/desorption behavior and separation conditions of vanadium and tungsten ions were investigated using a gel-type anion-exchange resin. In the adsorption experiment with the initial acidity of the solution, the adsorption rate of vanadium was remarkably low in strong acids and bases. Additionally, the adsorption rate of tungsten was low in a strong base. An increase in the reaction temperature increased the adsorption reaction rate and maximum adsorption. The effect of tungsten on the maximum adsorption was minimal. The adsorption isotherms of vanadium and tungsten on the ion-exchange resin were suitable for the Langmuir adsorption isotherms of both the ions. For tungsten, the adsorption isotherms of vanadium and tungsten were polyoxometalate. Both ion-exchange resins were simulated using similar quadratic reaction rate models. Vanadium was desorbed in the aqueous solutions of HCl or NaOH, the desorption characteristics of vanadium and tungsten depended on the desorption solution, and tungsten was desorbed in the aqueous solution of NaOH. It was possible to separate the two ions using the desorption process. The desorption reaction reached equilibrium within 30 min, and more than 90% recovery was possible.

Preparation and identification of U(IV) for the investigation of behaviors of uranium in a disposal repository (처분장에서 우라늄 거동 규명을 위한 U(IV)의 제조 및 확인)

  • Kim, Seung Soo;Kang, Kwang Chul;Kim, Jung Suck;Jung, Euo Chang;Baik, Min Hoon
    • Analytical Science and Technology
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    • v.21 no.2
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    • pp.143-147
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    • 2008
  • U(IV) ion, the valance state of uranium presumed at in a deep-depth disposal of a spent fuel, was prepared and separated from U(VI) ion. In order to prepare U(IV) ion, tests were performed by adding several reducing agents into a uranyl solution or by dissolution of uranium oxide in a mixed acid added with a reducing agent. The valance states of the uranium in the prepared solutions were identified by separating two ions with a Dowex AG 50W-X8 cation exchange resins and measuring the solutions using a laser-induced fluorescence spectroscopy. However, U(IV) and U(VI) were not separated by a Lichroprep Si60 exchange resin in the same separation condition of Pu(IV) and Pu(VI).

Adsorption/Desorption Characteristics of Vanadium from Ammonium Metavanadate using Anion Exchange Resin (음(陰)이온교환수지(交換樹脂)를 이용한 Ammonium Metavanadate로부터 바나듐 흡탈착(吸脫着) 특성(特性))

  • Jeon, Jong Hyuk;Kim, Young Hun;Hwang, In Sung;Lee, Jin Young;Kim, Joon Soo;Han, Choon
    • Resources Recycling
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    • v.22 no.1
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    • pp.55-63
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    • 2013
  • Considering considerable contents of vanadium and tungsten in spent SCR DeNOx catalysts, separation and recovery of those metals are required. In this respect, commercial anion exchange resin (MP600) was employed to recover vanadium from the synthetic solution of ammonium metavanadate. Experimental results indicated that vanadium exist as anion under the acidic condition (pH 2 ~ 6) and adsorbed on the resin. Although the adsorption rate was increased with temperature, the maximum amount of adsorption was not affected by temperature. Desorption took place under either strong acidic (less than pH 1) or strong caustic (higher than pH 13) condition. However, desorption seldom took place under moderate conditions (pH 3~11). Furthermore, adsorption equilibrium results agreed well with Freundlich isotherm and pseudo-second-order reactions. And, adsorption energy was evaluated using Dubinin-Radushkevich and Temkin isotherm.

Measurement of the Radiolysis Gases Generated in Several Waste Forms by External Irradiation (${\gamma}$-조사에 의한 방사성폐기물의 방사분해가스 발생량 평가)

  • Kwak, Kyung-Kil;Ryue, Young-Gerl;Kim, Ki-Hong;Je, Whan-Gyeong;Kim, Dong-Ho
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.4
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    • pp.345-352
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    • 2006
  • The cemented and paraffin wastes form which are incorporated the concentrated wastes, the cemented waste form which is incorporated the spent ion-exchange resins, and the miscellaneous waste(decontamination paper) were irradiated up to $10^{+8}$ rads at $5.43{\times}10^{+5}$ rads/hr with Co-60(72,023.9 Ci) as an external irradiation source. As a result, the radiolysis gases such as $H_2,\;CH_4,\;N_2,\;C_2H_6,\;O_2,\;CO\;and\;CO_2$, were measured in all the wastes. The major gas which was generated in all the wastes was hydrogen($H_2$). The volume of the generated gases showed a difference from $0.029{\sim}0.788\;cm^3.atm/1.1g$ according to the type of wastes, and more was generated in the cemented waste form incorporated a spent ion-exchange resin than in the other wastes. More hydrogen($H_2$) gas was generated in the decontamination paper waste than in the other wastes, and the G($H_2$) value was 0.12.

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