• 제목/요약/키워드: LiCl-KCl molten salt

검색결과 46건 처리시간 0.028초

Density of Molten Salt Mixtures of Eutectic LiCl-KCl Containing UCl3, CeCl3, or LaCl3

  • Zhang, C.;Simpson, M.F.
    • 방사성폐기물학회지
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    • 제15권2호
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    • pp.117-124
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    • 2017
  • Densities of molten salt mixtures of eutectic LiCl-KCl with $UCl_3$, $CeCl_3$, or $LaCl_3$ at various concentrations (up to 13 wt%) were measured using a liquid surface displacement probe. Linear relationships between the mixture density and the concentration of the added salt were observed. For $LaCl_3$ and $CeCl_3$, the measured densities were significantly higher than those previously reported from Archimedes' method. In the case of $LiCl-KCl-UCl_3$, the data fit the ideal mixture density model very well. For the other salts, the measured densities exceeded the ideal model prediction by about 2%.

Electrochemical Behaviors of Bi3+ Ions on Inert Tungsten or on Liquid Bi Pool in the Molten LiCl-KCl Eutectic

  • Kim, Beom Kyu;Park, Byung Gi
    • 방사성폐기물학회지
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    • 제20권1호
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    • pp.33-41
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    • 2022
  • Liquid Bi pool is a candidate electrode for an electrometallurgical process in the molten LiCl-KCl eutectic to treat the spent nuclear fuels from nuclear power plants. The electrochemical behavior of Bi3+ ions and the electrode reaction on liquid Bi pool were investigated with the cyclic voltammetry in an environment with or without BiCl3 in the molten LiCl-KCl eutectic. Experimental results showed that two redox reactions of Bi3+ on inert W electrode and the shift of cathodic peak potentials of Li+ and Bi3+ on liquid Bi pool electrode in molten LiCl-KCl eutectic. It is confirmed that the redox reaction of lithium with respect to the liquid Bi pool electrode would occur in a wide range of potentials in molten LiCl-KCl eutectic. The obtained data will be used to design the electrometallurgical process for treating actinide and lanthanide from the spent nuclear fuels and to understand the electrochemical reactions of actinide and lanthanide at liquid Bi pool electrode in the molten LiCl-KCl eutectic.

Li-K-Cd 합금을 이용한 LiCl-KCl 용융염에서 금속염화물의 제거 (Use of Li-K-Cd Alloy to Remove MCl3 in LiCl-KCl Eutectic Salt)

  • 김가영;김택진;장준혁;김시형;이창화;이성재
    • 방사성폐기물학회지
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    • 제16권3호
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    • pp.309-313
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    • 2018
  • Li-Cd 합금을 이용한 환원추출방식을 LiCl-KCl 기반의 drawdown 공정에 적용하게 되면, LiCl-KCl 공융염의 조성이 파괴되므로 공정온도를 높여야 하며, 전해정련 및 전해제련과 같은 공정에 LiCl-KCl 용융염을 재사용할 수 없게 된다. 따라서, 본 연구에서는 공융염 조성에 적합한 Li-K-Cd 합금을 제조하였으며, 이를 이용하여 U와 Nd가 포함된 LiCl-KCl 염에 투입하여 용융염 내 $UCl_3$의 제거가 가능한지 평가하였다.

LiCl-KCl 공융염 내에서 희토류염화물들의 침전 (Precipitation of Rare Earth Chlorides in a LiC-KCl Eutectic Molten Salt)

  • 조용준;양희철;은희철;김응호;김인태
    • 공업화학
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    • 제18권4호
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    • pp.361-365
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    • 2007
  • LiCl-KCl 공융염 내 존재하는 몇가지 희토류염화물($Ce/Nd/GdCl_3$)들의 산소와의 반응으로 인한 침전반응에 대한 연구를 수행하였다. 산소와의 반응으로 형성되는 희토류침전물의 형태와 산소분산 시간(최대 420 min) 및 공융염($450{\sim}750^{\circ}C$) 온도가 침전물로의 전환율에 미치는 영향을 규명하였다. 본 연구결과 산소분산 시간 및 공융염의 온도와 무관하게 $NdCl_3$$GdCl_3$는 옥시염화물(REOCl), $CeCl_3$는 산화물($REO_2$)형태로 침전되었으며 이러한 실험결과는 반응 Gibbs free energy (${\Delta}G_r$) 를 이용한 예측 결과와도 일치하였다. 희토류염화물의 침전물로의 전환특성은 전환율 개념을 도입하여 파악하였다. 전환율은 산소분산 시간이 증가함에 따라서 지수적으로 증가하였으며 $750^{\circ}C$의 공융염 온도 및 300 min 이상의 분산시간 조건에서 0.999 이상의 전환율을 나타내었다. 공융염 온도가 증가함에 따라서 전환율이 증가하였다. Ce의 경우에는 60 min 이상의 산소분산 조건에서 전 실험온도 범위에서 0.999 이상의 일정한 전환율을 나타내었다

Interaction of Rare Earth Chloride Salts to Alumina and Mullite in LiCl-KCl at 773 K

  • Horvath, David;Warmann, Stephen;King, James;Marsden, Kenneth;Hoover, Robert
    • 방사성폐기물학회지
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    • 제18권3호
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    • pp.337-346
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    • 2020
  • Two commonly used ceramics in molten salt research are alumina and mullite. The two ceramics were exposed to a combination of rare earth chlorides (YCl3, SmCl3, NdCl3, PrCl3, and CeCl3; each rare earth chloride of 1.8 weight percent) in LiCl-KCl at 773 K for approximately 13 days. Scanning electron microscopy with wave dispersion spectra was utilized to investigate a formation layer or deposition of rare earths onto the ceramic. Only the major constituents of the ceramics (Al, Si, and O2) were observed during the wave dispersion spectra. X-ray fluorescence was used as well to determine concentration changes in the molten salt as a function of ceramic exposure time. This study shows no evidence of ionic exchange or layer formation between the ceramics and molten chloride salt mixture. There are signs of surface tension effects of molten salt moving out of the tantalum crucible into secondary containment.

Electrochemical Behavior of Li-B Alloy Anode - Liquid Cadmium Cathode (LCC) System for Electrodeposition of Nd in LiCl-KCl

  • Kim, Gha-Young;Shin, Jiseon;Kim, Tack-Jin;Shin, Jung-Sik;Paek, Seungwoo
    • 전기화학회지
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    • 제18권3호
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    • pp.102-106
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    • 2015
  • The performance of Li-B alloy as anode for molten salt electrolysis was firstly investigated. The crystalline phase of the prepared Li-B alloy was identified as $Li_7B_6$. The potential profile of Li-B alloy anode was monitored during the electrodeposition of $Nd^{3+}$ onto an LCC (liquid cadmium cathode) in molten LiCl-KCl salt at $500^{\circ}C$. The potential of Li-B alloy was increased from -2.0 V to -1.4 V vs. Ag/AgCl by increasing the applied current from 10 to $50mA{\cdot}cm^{-2}$. It was found that not only the anodic dissolution of Li to $Li^+$ but also the dissolution of the atomic lithium ($Li^0$) into the LiCl-KCl eutectic salt was observed, following the concomitant reduction of $Nd^{3+}$ by the $Li^0$ in Li-B alloy. It was expected that the direct reduction could be restrained by maintaining the anode potential higher that the deposition potential of neodymium.

Rare earth removal from pyroprocessing fuel product for preparing MSR fuel

  • Dalsung Yoon;Seungwoo Paek;Chang Hwa Lee
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.1013-1021
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    • 2024
  • A series of experiments were performed to produce a fuel source for a molten salt reactor (MSR) through pyroprocessing technology. A simulated LiCl-KCl-UCl3-NdCl3 salt system was prepared, and the U element was fully recovered using a liquid cadmium cathode (LCC) by applying a constant current. As a result, the salt was purified with an UCl3 concentration lower than 100 ppm. Subsequently, the U/RE ingot was prepared by melting U and RE metals in Y2O3 crucible at 1473 K as a surrogate for RE-rich ingot product from pyroprocessing. The produced ingot was sliced and used as a working electrode in LiCl-KCl-LaCl3 salt. Only RE elements were then anodically dissolved by applying potential at - 1.7 V versus Ag/AgCl reference electrode. The RE-removed ingot product was used to produce UCl3 via the reaction with NH4Cl in a sealed reactor.

LiCl-KCl 용융염에서 Cd-Li 금속을 이용한 U 및 란탄족의 환원반응 (Reductive reaction of U and Lanthanides using Cd-Li metal in LiCl-KCl Molten Salt)

  • 우문식;이병직;김응호;유재형
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.339-339
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    • 2004
  • 원자로를 이용하여 장수명핵종(long lived nucleus)을 소멸처리하는 과정에서 초우라늄(TRU, transuranium)과 희토류(RE, rare earth) 금속에 포함되어 있는 소량의 핵분열성(fissile) 물질인 우라늄을 제거할 필요가 있다. 본 실험은 LiCl-KCl 용융염계에서 전해제련법(Electrowinning)을 이용하여 용융염욕에 존재하는 우라늄을 제거하기 위하여 필요한 Cd-Li 양전극 물질을 제조하였고, 제조된 금속을 이용하여 우라늄 및 란탄족(Dy, Ce, Y, Nd, Gd) 금속의 환원 특성을 파악하였다.(중략)

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Electrochemical Behavior of Ce ion and Bi ion in LiCl-KCl Molten Salt

  • Kim, Beom-Kyu;Han, Hwa-Jeong;Park, Ji-Hye;Kim, Won-Ki;Park, Byung Gi
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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    • pp.227-228
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    • 2017
  • In this paper, electrolytic behavior of Cerium and Ce-Bi ion system was studied. The electrochemical behavior of Ce was studied in $LiCl-KCl-CeCl_3$ molten salts using electrochemical techniques Cyclic Voltammetry on tungsten electrodes at 773K. During the process of CV electrolysis, intermetallic compound were observed of Ce, Cex-Biy. Further study, in order to determine clarity of diffusion coefficient in this experiment, we will compare result of electrochemistry method and we also need to quantitative research.

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LiCl-KCl 고온 용융염 내 UCl3 및 GdCl3의 전기화학적 거동 연구 (Electrochemical Behavior of UCl3 and GdCl3 in LiCl-KCl Molten Salt)

  • 민슬기;배상은;박용준;송규석
    • 전기화학회지
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    • 제12권3호
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    • pp.276-281
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    • 2009
  • 본 연구는 고온화학공정에 사용할 전기화학적 센서 기술 개발의 사전 연구로서 고온 LiCl-KCl 공융염에 $UCl_3$$GdCl_3$를 녹여 $U^{3+}$$Gd^{3+}$의 전기화학 반응을 조사하였다. $U^{3+}$는 고온 LiCl-KCl 용융염내에서 -0.2V/-0.35 V에서 $U^{4+}$로의 산화/환원반응의, -1.51 V/-1.35 V에서 전착/해리 반응전류의 피크를 나타내었다. $Gd^{3+}$의 경우 -2.15 V에서 전착반응 피크를, -1.9 V에서 산화해리전류 피크를 나타내었다. $U^{3+}$$Gd^{3+}$의 혼합 고온 용융염에서는 $Gd^{3+}$의 전착 피크가 양의 전위로 이동하였다. 일정전류법의 결과는 시간이 지남에 따라 전위값이 일정해졌으며 그 전위값은 전해질 내 반응물의 환원전위값과 일치하였다. 노멀펄스전위법과 직각파전위법은 두 원소의 정성분석을 위한 좋은 전기화학적 방법론임을 보였으며 특히 노멀펄스전위곡선을 미분한 결과는 사용된 다른 방법에 비해 반응전류의 피크분리가 잘 일어났다.