• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.74-74
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• 2017

Electrorefining is a key step in pyroprocessing. The electrorefining process is generally composed of two recovery steps - the deposit of uranium onto a solid cathode and the recovery of the remaining uranium and TRU elements simultaneously by a liquid cadmium cathode. Uranium deposit recovered from the solid cathode is a dendritic powder. It is necessary to separate the adhered salt from the deposits prior to the consolidation of uranium deposit. The adhered salt is composed of lithium, potassium, uranium, and rare earth chlorides. Distillation process was employed for the cathode processing. One of the operation methods is distillation of the salt at low temperature ($900^{\circ}C$), and then melting of the deposit at high temperature to avoid a backward reaction. For the development of the salt distiller, the distillation behavior of the low vapor pressure chlorides should be studied. Rare earth chlorides in the adhered salt of uranium deposits have relatively low vapor pressures compared to the process salt (LiCl-KCl). In this study, the evaporation rates of the lanthanum and neodymium chlorides were measured for the salt separation from electrorefiner uranium deposits in the temperature range of $825{\sim}910^{\circ}C$. The evaporation rate of both chlorides increased with an increasing templerature. The evaporation rate of lanthanum chloride varied from 0.12 to $1.68g/cm^2/h$. Neodymium chloride was more volatile than lanthanum chloride. The evaporation rate of neodymium chloride varied from 0.20 to $4.55g/cm^2/h$. The evaporation rate of both chlorides are more than $1g/cm^2/h$ at $900^{\circ}C$. Even though the evaporation rates of both chlorides were less than that of the process salt, the contents of the lanthanide chlorides were small in the adhered salt. Therefore it can be concluded that $900^{\circ}C$ is suitable for the operation temperature of the salt distiller.

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2001년도 The 6th International Symposium of East Asian Resources Recycling Technology
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• pp.179-182
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• 2001

The chloride volatilization method for the recovery of zirconium and removal of uranium from zirconium containing metallic wastes formed in spent fuel reprocessing was studied using the simulated alloy waste, i.e. the mixture of Zr foil and UO$_2$/U$_3$O$_{8}$ powder. When the simulated waste was heated to react with chlorine gas at 350- l00$0^{\circ}C$, the zirconium metal changed to volatile ZrCl$_4$showing high volatility ratio (Vzr) of 99%. The amount of volatilized uranium increases at higher temperatures causing lowering of decontamination factor (DF) of uranium. This is thought to be caused by the chlorination of UO$_2$ with ZrCl$_4$vapor. The highest DF value of 12.5 was obtained when the reaction temperature was 35$0^{\circ}C$. Addition of 10 vol.% oxygen gas into chlorine gas was effective for suppressing the volatilization of uranium, while the volatilization ratio of zirconium was decreased to 68% with the addition of 20 vol.% oxygen. In the case of the mixture of Zr foil and U$_3$O$_{8}$, the V value of uranium showed minimum (44%) at 40$0^{\circ}C$ with chlorine gas giving the highest DF value 24.3. When the 10 vol.% oxygen was added to chlorine gas, the V value of zirconium decreased to 82% at $600^{\circ}C$, but almost all the uranium volatilized (Vu=99%), which may be caused by the formation of volatile uranium chlorides under oxidative atmosphere.ere.

• 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.

• Journal of Radiation Protection and Research
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• 제8권2호
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• pp.36-40
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• 1983

알파방출핵종(放出核種)인 우라늄을 혼합(混合) Oxalate-Chloride 용액(溶液)으로 부터 저렴(低廉)한 가격(價格)의 stainless steel 음극판(陰極板)에 전기정착(電氣定着)시켰다. 전기정착(電氣定着) 최적조건(最適條件)은 정착시간(定着時間), 초기전류(初期電流), 전극간(電極間)의 거리, 전해액(電解液)의 pH, 음극(陰極)의 정착면적(定着面積) 및 전해액중(電解液中)의 우라늄시료농도(試料濃度)에 따라 결정(決定)되였다. 표준(標準)우라늄 순수용액(純粹溶液)(NBS 960 질산화물(窒酸化物)을 사용하여 3회(回) 반복(反復)된 실험(實驗)으로 정착시간(定着時間) 60분(分)만에 90% 신뢰도(信賴度)에서 계측기(計測器)의 오차(誤差)가 4%일 때 평균(平均) 99% 이상(以上)의 회수율(回收率)을 얻었다.

• 방사성폐기물학회지
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• 제18권4호
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• pp.549-562
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• 2020

Deionized water, methanol, and ethanol were investigated for their effectiveness at dissolving LiCl-KCl-UCl3 at 25, 35, and 50℃ using inductively coupled plasma mass spectrometry (ICP-MS) to study the concentration evolution of uranium and mass ratio evolutions of lithium and potassium in these solvents. A visualization experiment of the dissolution of the ternary salt in solvents was performed at 25℃ for 2 min to gain further understanding of the reactions. Aforementioned solvents were evaluated for their performance on removing the adhered ternary salt from uranium dendrites that were electrochemically separated in a molten LiCl-KCl-UCl3 electrolyte (500℃) using scanning electron microscopy with energy dispersive spectroscopy (SEM-EDS). Findings indicate that deionized water is best suited for dissolving the ternary salt and removing adhered salt from electrodeposits. The maximum uranium concentrations detected in deionized water, methanol, and ethanol for the different temperature conditions were 8.33, 5.67, 2.79 μg·L-1 for 25℃, 10.62, 5.73, 2.50 μg·L-1 for 35℃, and 11.55, 6.75, and 4.73 μg·L-1 for 50℃. ICP-MS analysis indicates that ethanol did not take up any KCl during dissolutions investigated. SEM-EDS analysis of ethanol washed uranium dendrites confirmed that KCl was still adhered to the surface. Saturation criteria is also proposed and utilized to approximate the state of saturation of the solvents used in the dissolution trials.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.319.1-319
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• 2002

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.582-582
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• 2018

• 방사성폐기물학회지
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• 제1권1호
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• pp.25-39
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• 2003

본 연구에서는 고온의 LiCl-Ll$_2$O 용융염계에서 우라늄 산화물의 금속전환과 Li$_2$O의 전해반응이 동시에 진행되는 통합 반응 메카니즘을 기초로 한 전기화학적 금속전환기술을 제안하였다. 본 실험에서는 전기화학적 환원반응에 의해 생성된 Li 금속이온이 음극에 전착과 동시에 우라늄 산화물과 반응하여 금속전환율 99 % 이상의 우라늄 감속을 생성하는 통합 반응 메카니즘을 확인할 수 있었다. 또한 전기화학적 금속전환기술의 공정 적용성 평가 일환으로 우라늄 산화물의 금속전환성, 반응 메카니즘 규명, Li$_2$O의 closed recycle rate 및 물질전달 특성 등의 기초 데이터를 확보하였다 향후 전기화학적 금속전환기술은 LiCl-Li 용융염계의 금속전환공정의 반응조건 제한성 해소, 금속전환율 향상 및 공정의 단순화 등의 기술성과 경제성 향상 측면에서 획기적인 방안으로 고려될 수 있을 것으로 판단된다.

• 방사성폐기물학회지
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• 제20권2호
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• pp.193-207
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• 2022

Thermodynamically, TRUO_x, REO_x, and SrO_x can be chlorinated using ammonium chloride (NH₄Cl) as a chlorinating agent, whereas uranium oxides (U₃O₈ and UO₂) remain in the oxide form. In the preliminary experiments of this study, U₃O₈ and CeO₂ are reacted separately with NH₄Cl at 623 K in a sealed reactor. CeO₂ is highly reactive with NH₄Cl and becomes chlorinated into CeCl₃. The chlorination yield ranges from 96% to 100%. By contrast, U₃O₈ remains as UO₂ even after chlorination. We produced U/REO_x- and U/SrO_x-simulated fuels to understand the chlorination characteristics of the oxide compounds. Each simulated fuel is chlorinated with NH₄Cl, and the products are dissolved in LiCl-KCl salt to separate the oxide compounds from the chloride salt. The oxide compounds precipitate at the bottom. The precipitate and salt phases are sampled and analyzed via X-ray diffraction, scanning electron microscope-energy dispersive spectroscopy, and inductively coupled plasma-optical emission spectroscopy. The analysis results indicate that REO_x and SrO_x can be easily chlorinated from the simulated fuels; however, only a few of U oxide phases is chlorinated, particularly from the U/SrO_x-simulated fuels.

• Bulletin of the Korean Chemical Society
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• 제21권4호
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• pp.393-400
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• 2000

2,2￠-Dihydroxyazobenzene (DHAB) was attached to poly(ethylenimine) (PEI) to obtain DHAB-PEI. Spectral titration revealed that uranyl, Fe(III), Cu(II), and Zn(II) ion form 1 : 1-type complexes with DHAB attached to PEI. Formation constants for the metal complexes formed by the DHAB moieties of DHAB-PEI were mea-sured by using various competing ligands. The results indicated thatthe concentrations of uranyl, Fe(III), and Cu(II) ions can be reduced to 10 -16 -10 -23 M at p 8 with DHAB-PEI when the concentration of the DHAB moiety is 1 residue M. By using cyanuric chloride as the coupling reagent, DHAB-PEI was immobilized on Sephadex G-25 resin to obtain DHAB-PEI-Seph. Binding of uranyl,Fe(III), Cu(II), and Zn(II) ion by DHAB-PEI-Seph was characterized by using competing ligands. A new method has been developed for characteriza-tion of metal sequestering ability of a chelating resin. Formation constants and metal-binding capacity of two sets of binding sites on the resin were estimated for each metal ion. DHAB-PI-Seph was applied to recovery of metals such as uranium,Fe, Cu, Zn, Pb, V, Mn, and W from seawater. The uranium recovery from seawaterby DHAB-PEI-Seph does not meet the criterion for economical feasibility partlydue to interference by Fe and Zn ions. The seawater used in the experiment was contaminated by Fe and Zn and, therefore, the efficiency of uranium extractionfrom seawater with DHAB-PEI-Seph could be improved if the experiment is carried out in a cleaner sea.