• 제목/요약/키워드: lanthanides

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Lanthanides-Benzoylformate 착물 형성에 관한 열역학적 연구 (Thermodynamic Properties of Lanthanides Complexes with Benzoylformate Anion)

  • 김영인;박선금
    • 대한화학회지
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    • 제37권4호
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    • pp.442-447
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    • 1993
  • 수용액 내에서 란탄(Ⅲ)-benzoylformate 착물 형성 반응의 열역학적 파라메타들(${\Delta}$G, ${\Delta}$H 및 ${\Delta}$S)을 pH 및 엔탈피 적정 방법을 사용하여 이온세기 $0.1M NaClO_4$, 25$^{\circ}C$ 조건하에서 구하였다. 란탄-benzoylformate 착물의 안정도 상수(1:1) 값으로부터 benzoylformate가 두자리 리간드로 작용함을 알 수 있었다. 열역학적 실험 결과는 카르복실기와 함께 케톤기 산소원자가 결합에 참여하여 킬레이트를형성하는 것으로 판단되었으며, 이는 benzoylformate 리간드 내에 존재하는 벤젠고리의 공액 효과에 의해 케톤기의 산소원자의 전하량이 증가된 결과로 해석되었다. 착물의 안정도는 엔트로피 효과 뿐 아니라, 금속-산소결합 형성에 따른 엔탈피 효과에도 기인하였다.

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New Cryptand Complexes of Lanthanides(Ⅲ) and Dioxouranium(Ⅵ) Nitrates

  • Oh-Jin Jung;Chil-Nam Choi;Hak-Jin Jung
    • Bulletin of the Korean Chemical Society
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    • 제12권2호
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    • pp.130-137
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    • 1991
  • The following new cryptand 221 complexes of lanthanides(Ⅲ) and dioxouranium(Ⅵ) nitrate have been synthesized: $(Ln(C_{16}H_{32}N_2O_5)(H_2O)_2(NO_3)_3\ and \((UO_2)_2(C_{16}H_{32}N_2O_5)(H_2O)_4(NO_3)_4$. These complexes have been identified by elemental analysis, moisture titration, conductivity measurements and various spectroscopic techniques. The proton and carbon-13 NMR as well as calorimetric measurements were used to study the interaction of cryptand 221 with La(Ⅲ), Pr(Ⅲ ), Ho(Ⅲ) and $UO_2(Ⅱ)$ ions in nonaqueous solvents. The bands of metal-oxygen atoms, metal-nitrogen atoms and O-U-O in the IR spectra shift upon complexation to lower frequencies, and the vibrational spectra ({\delta}NMN$) of metal-amide complexes in the crystalline state exhibit lattice vibrations below 300 $cm^{-1}$. The NMR spectra of the lanthanides(Ⅲ) and dioxouranium(Ⅵ) nitrate complexes in nonaqueous solvents are quite different, indicating that the ligand exists in different conformation, and also the $^1H$ and $^{13}C-NMR$ studies indicated that the nitrogen atom of the ring has greater affinity to metal ions than does the oxygen atom, and the planalities of the ring are lost by complexation with metal ions. Calorimetric measurements show that cryptand 221 forms more stable complexes with $La^{3+}$ and $Pr^{3+}$ ions than with $UO^{22+}$ ion, and $La^{3+}/Pr^{3+}$ and $UO^{22+}/Pr^{3+}$ selectivity depends on the solvents. These changes on the stabilities are dependent on the basicity of the ligand and the size of the metal ions. The absorption band (230-260 nm) of the complex which arises from the direct interaction of macrocyclic donor atoms with the metal ion is due to n-{\delta}*$ transition and also that (640-675 nm) of $UO^{22+}$-cryptand 221 complex, which arises from interaction between two-dioxouranium(Ⅵ) ions in being out of cavity of the ligand ring is due to d-d* transition.

Lanthanides-L-proline 착물의 형성에 관한 열역학적 연구 (Thermodynamic Parameters of Complexation of Lanthanides by L-proline)

  • 최임연;김영인;최성락;현명호
    • 대한화학회지
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    • 제37권1호
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    • pp.105-111
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    • 1993
  • 수용액내에서 란탄족 금속(III)이온과 광학 활성을 지닌 L-proline간의 안정도 상수(1:1)값들을 pH 적정 방법을 사용하여 이온강도 0.1M $NaClO_4$, 25$^{\circ}C$ 조건에서 구하였다. 안정도 상수값은 경란탄족과 중란탄족 금속 사이에 "gadolinium break" 현상을 나타내었으며, 리간드 산도와 안정도 상수값의 관계로 부터 L-proline이 두자리 리간드로 작용함을 알 수 있었다. 열역학적 함수값(${\Delta}H$, ${\Delta}S$)들을 같은 조건에서 엔탈피 적정 방법으로 구하였다. lanthanide(III)-L-proline 착물 형성은 흡열 반응 및 큰 엔트로피 변화량(${\Delta}S$)을 나타내었으며 엔트로피 변화량은 L-proline 고리의 견고성으로 인해 과량의 탈수 효과에 의한 것으로 판단되었다. lanthanide(III)-anthranilate 착물 형성의 열역학적 함수값과 비교하여 본 결과, L-proline의 헤테로 고리 질소 원자와 카르복실기가 결합에 참여하여 킬레이트를 형성하였으며, anthranilate와 L-proline착물의 엔탈피 변화량(${\Delta}H$) 차이는 두 리간드 내에 존재하는 질소 원자의 염기도 차이에 의한 것으로 판단되었다.

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사용후핵연료 Voloxidation 공정 분석 (Spent Fuel Voloxidation Process Analysis)

  • 강조홍;박병흥
    • 융복합기술연구소 논문집
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    • 제4권2호
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    • pp.47-50
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    • 2014
  • Voloxidation is a process for converting $UO_2$ into $U_3O_8$ while removing some volatile products in spent fuels (SF). Various oxidative gas conditions including air and mixture of Ar and $O_2$ could be adopted for the process. The gas flows into a reactor under high temperature ($>500^{\circ}C$) and components of SF are reacted with the gas. SF is composed of various components such as actinides, lanthanides, and alkali metals. Therefore, it is of significance to understand their behavior during the reactions for process development. However, due to the limit of available experiments, phase diagram analysis should be preceded. TPP diagram is constructed with respect to temperature-pressure-pressure. It shows a stable phase depending on partial pressures of gas components as well as temperature. In this work, we investigated TPP diagrams for actinides, lanthanides and other oxides to determine stable oxide forms under different gas conditions. The results would be used to set up a material balance under a pyroprocessing scheme of SF and compare the gas conditions for the optimization of fission products removal.

Separation of Burnup Monitors in Spent Nuclear Fuel Samples by Liquid Chromatography

  • Joe, Kih-Soo;Jeon, Young-Shin;Kim, Jung-Suck;Han, Sun-Ho;Kim, Jong-Gu;Kim, Won-Ho
    • Bulletin of the Korean Chemical Society
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    • 제26권4호
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    • pp.569-574
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    • 2005
  • A coupled column liquid chromatography system was applied for the separation of the burnup monitors in spent nuclear fuel sample solutions. A reversed phase column was studied for the adsorption behavior of uranyl ions using alpha-hydroxyisobutyric acid as an eluent and used for the separation of plutonium and uranium. A cation exchange column prepared by coating 1-eicosylsulfate onto the reversed phase column was used for the separation of the lanthanides. In addition, retention of Np was checked with the reversed phase column and cation exchange column, respectively, according to the oxidation states to observe the interference effect for the separation of burnup monitors. This chromatography system showed a great reduction in separation time compared to a conventional anion exchange method. A good agreement from the burnup data was obtained between for this method and a conventional anion exchange method to within 1% of a difference for the spent nuclear fuel samples of about 40 GWD/MTU.

Comparison of Membrane Currents in Xenopus Oocytes in Response to Injection of Calcium Influx Factor (CIF) and Depletion of Intracellular Calcium Stores

  • Kim, Hak-Yong;Hanley, Michael R.
    • BMB Reports
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    • 제33권3호
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    • pp.202-207
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    • 2000
  • The depletion of intracellular calcium stores by thapsigargin treatment evoked extracellular calcium-dependent membrane currents in Xenopus laevis oocytes. These currents have been compared to those evoked by microinjection of a calcium influx factor (CIF) purified from Jurkat T lymphocytes. The membrane currents elicited by thapsigargin treatment (peak current, $163{\pm}60$ nA) or CIF injection (peak current, $897{\pm}188$ nA) were both dependent on calcium entry, based on their eradication by the removal of extracellular calcium. The currents were, in both cases, attributed primarily to well-characterized $Ca^{2+}-dependent$ $Cl^-$ currents, based on their similar reversal potentials (-24 mV vs. -28 mV) and their inhibition by niflumic acid (a $Cl^-$ channel blocker). Currents induced by either thapsigargin treatment or CIF injection exhibited an identical pattern of inhibitory sensitivity to a panel of lanthanides, suggesting that thapsigargin treatment or CIF injection evoked $Cl^-$ currents by stimulating calcium influx through pharmacologically identical calcium channels. These results indicate that CIF acts on the same calcium entry pathway activated by the depletion of calcium stores and most lanthanides are novel pharmacological tools for the study of calcium entry in Xenopus oocytes.

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SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN

  • Simpson, Michael F.;Yoo, Tae-Sic;Labrier, Daniel;Lineberry, Michael;Shaltry, Michael;Phongikaroon, Supathorn
    • Nuclear Engineering and Technology
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    • 제44권7호
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    • pp.767-772
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    • 2012
  • In support of optimizing electrorefining technology for treating spent nuclear fuel, lithium drawdown has been investigated for separating actinides from molten salt electrolyte. Drawdown reaction selectivity is a major issue that requires investigation, since the goal is to remove actinides while leaving the fission products and other components in the salt. A series of lithium drawdown tests with surrogate fission product chlorides was run to obtain selectivity data with non-radioactive salts, develop a predictive model, and draw conclusions about the viability of using this process with actinide-loaded salt. Results of tests with CsCl, $LaCl_3$, $CeCl_3$, and $NdCl_3$ are reported here. Equilibrium was typically achieved in less than 10 hours of contact between lithium metal and molten salt under well-stirred conditions. Maintaining low oxygen and water impurity concentrations (<10 ppm) in the atmosphere was observed to be critical to minimize side reactions and maintain stable salt compositions. An equilibrium model has been formulated and fit to the experimental data. Good fits to the data were achieved. Based on analysis and results obtained to date, it is concluded that clean separation between minor actinides and lanthanides will be difficult to achieve using lithium drawdown.