• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.9 no.2
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• pp.63-71
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• 2011

A large volume of uranium electrokinetic leachate has been generated during the electrokinetic decontamination to remove uranium from contaminated soil. The treatment technology for the reuse of the uranium leachate was developed. The concentration of uranium in the generated uranium leachate was 180 ppm and concentrations of Mg(II), K(I), Fe(II), and Al(III) ions ranged from 20 ppm to 1,210 ppm. The treatment process for uranium leachate consisted mainly of mixing and cohesion, precipitation, concentration, and filtration. In order to obtain the pH=11 of a precipitate solution, the calcium hydroxide needs to be 3.0g/100ml and the sodium hydroxide needed to be 2.7g/100ml. The results of several precipitation experiments showed that a mixture of NaOH+0.2g alum+0.15g magnetite was an optimal precipitant for filtration. The average particle size of precipitate with NaOH+alum+0.15g magnetite was $600\;{\mu}m$. Because the total value of metal concentrations in supernatant at pH=9 was the smallest, sodium hydroxide should be added with 0.2g alum and 0.15g magnetite for pH=9 of leachate.

• Journal of the Korean Electrochemical Society
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• v.18 no.3
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• pp.121-129
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• 2015

The platinum anode for the electrolytic reduction process is generally surrounded by a nonporous ceramic shroud with an open bottom to offer a path for $O_2$ gas produced on the anode surface and prevent the corrosion of the electrolytic reducer. However, the $O^{2-}$ ions generated from the cathode are transported only in a limited fashion through the open bottom of the anode shroud because the nonporous shroud hinders the transport of the $O^{2-}$ ions to the anode surface, which leads to a decrease in the current density and an increase in the operation time of the process. In the present study, we demonstrate the electrolytic reduction of 1 kg-uranium oxide ($UO_2$) using the porous shroud to investigate its long-term stability. The $UO_2$ with the size of 1~4mm and the density of $10.30{\sim}10.41g/cm^3$ was used for the cathode. The platinum and 5-layer STS mesh were used for the anode and its shroud, respectively. After the termination of the electrolytic reduction run in 1.5 wt.% $Li_2O-LiCl$ molten salt, it was revealed that the U metal was successfully converted from the $UO_2$ and the anode and its shroud were used without any significant damage.

• Analytical Science and Technology
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• v.21 no.2
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• pp.109-116
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• 2008

Resins were synthesized by mixing 1-aza-18-crown-6 macrocyclic ligand into styrene(dangerous matter) divinylbenzene(DVB) copolymer with crosslink of 1%, 2%, 6% and 12% by substitution reaction. The synthesis of these resins was confirmed by content of chlorine, elemental analysis, thermogravimetric analysis, electron microscopy, and IR. The effects of pH, time, crosslink of resins and dielectric constant of solvent on adsorption of uranium ion by resin adsorbent were investigated. Uranium ion showed a great adsorption above pH 3 and adsorption equilibrium of metal ions was established in about two hours. In addition, adsorptive selectivity of resin in ethanol solvent was $UO{_2}^{2+}$ > $Zn^{2+}$ > $Lu^{3+}$ ion and adsorption of uranium ion increased with the increase of the degree of crosslinking (1%~12%) and was inversely in proportional to the order of dielectric constant of solvents.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.358-362
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• 2003

An electrochemical reduction technology which can reduce the decay heat, volume, and radioactivity of spent fuel by a factor of quarter by converting oxide type spent fuel to a metallic form in a molten salt was developed and mock-up test in a 5kg $U_3O_8$/batch scale was carried out. The electrochemical reaction was analyzed regarding the operational factors. The research efforts was also concentrated on the apparatus development for a hot test. Fresh $U_3O_8$ powder was metallized with a more than 99% yield via this electrochemical technology and design data for the 20kg $U_3O_8$/batch scale apparatus were also obtained.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.4
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• pp.315-319
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• 2015

A high-throughput electrorefiner has been developed for commercialization use by enhancing the uranium recovery from the reduced metal which is produced from the oxide reduction process. It is necessary to scrap and effectively collect uranium dendrites from the surface of the solid cathode for high yield. When a steel electrode is used as the cathode in the electrorefining process, uranium is deposited and regularly stuck to the steel cathode during electrorefining. The sticking coefficient of a steel cathode is very high. In order to decrease the sticking coefficient of the steel cathode effectively, vibration mode was applied to the electrode in this study. Uranium dendrites were scraped and fell apart from the steel cathode by a vibration force. The vibrational scraping of the steel cathode was compared to the self-scraping of the graphite cathode. Effects of the applied current density and the vibration stroke on the scraping of the uranium dendrites were also investigated.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.41-47
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• 1998

플라즈마를 이용한 핵연료재료 건식처리 공정 기초연구로서 플라즈마 기체에 의한 U와 $UO_2$의 산화가속화 연구를 수행하였다. $UO_2$에서는 플라즈마를 사용할 경우 40$0^{\circ}C$에서 약 300%정도, 50$0^{\circ}C$에서는 70%정도의 산화가속화가 일어났으며 금속우라늄의 경우에는 35$0^{\circ}C$에서 50%정도의 산화가속화를 확인할 수 있었고 power가 증가함에 따라 산화량이 증가하는 것을 알 수 있었다. 한편 전체적인 실험 결과가 시간에 따라 산화량이 선형적으로 증가하는 것으로 나타나 400~50$0^{\circ}C$에서는 표면반응이 중요한 반응이라는 것을 확인하였다.

• Proceedings of the KSEG Conference
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• 2004.03a
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• pp.16001-16125
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• 2004

물리검층은 주로 석유탐사 분야에서 개발·이용되어왔으나 소구경 시추공을 이용하는 지반조사. 자원평가, 지하수조사 또는 환경오염조사 등에서 물리검층의 수요가 증가하고 있다. 국내에서 수행된 물리검층은 우라늄 탐사 목적으로 1980년 전후로 많이 수행되었으며 1990년 중반에는 지하수 조사에 일부 활용되어 왔다. 현재 물리검층의 활용도가 증가하고 있는 분야는 지반조사 분야로 원위치 물성측정, 시추공과 교차하는 암반의 균열파악 등 터널, 교량과 같은 각종 토목분야의 지반조사에 많이 활용되고 있다. 이외에도 지하수 유동특성 규명이나 환경오염조사, 자원평가(지열, 온천, 석·골재, 금속광상 등)에도 활용되고 있다. (중략)

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.40-45
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• 1998

Th-232를 Fertile 핵연료로 사용한 압력관형 고전환 경수로심을 설계하였다. 토륨 Blanket은 10년 정도 노내에 위치시키고, 농축 우라늄 Driver는 매년 재장전하도록 설계하였다. Driver로는 $UO_2$핵연료와 U-10%Zr 금속 핵연료를 사용하였고, Blanket으로 이중 탄소 피막 핵원료를 ThO$_2$에 적용한 핵연료를 사용하였다. 핵연료봉의 구조는 울진 3/4호기 핵연료와 같은 재원으로 하였으며 육각형 격자 배열로 집합체를 구성하였다. Seed Bundle을 1년 단위로 교체하고 Blanket Bundled을 5년-10년간 노내에 위치시키는 경우 경수로보다는 높은 전환율 갖는 원자로를 설계할 수 있다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.565-570
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• 1996

본 연구에서는 고밀집 섬유다발체 내에 수은과 금속이온을 함유한 수용액을 동시에 주입시켜 최소 공간에서 최대한의 수은전극 면적을 갖는 수직형 순환식 수은 모세관 다발체 전극 전해반응 장치가 개발되었다. 이장치의 특성과 안정성을 평가하기 위해 수은과 수용액의 유량 변화에 따른 철(III)과 우라늄(IV)이온의 환원 voltammogram 이 측정되었다. 본 연구에서 개발된 수직형 순환식 수은 모세관 다발체 전극 전해계는 정확히 제어되는 수용액 유량조건에서 수용액내의 금속이온의 산화수 상태 및 농도의 연속적인 분석 및 전해반응 기구 해석에 효과적으로 사용될 수 있음을 알 수 있었다.

• Journal of the Korean Chemical Society
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• v.38 no.1
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• pp.34-40
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• 1994

First observation of uranium using a diode laser was published recently. The experiment was performed by the optogalvanic spectroscopy using diode lasers. A laser source causes the current change in a hollow cathode discharge lamp when metal atoms in plasma absorb the diode laser light. The optogalvanic signal is collected by detecting the current change. This work is the extended investigation of our previous research, the uranium detection using a diode laser. New electronic transitions of uranium and thorium in 775∼850 nm were investigated using diode lasers. In addition, the Rb(Ⅰ) optogalvanic spectra at 780.02 nm and 794.76 nm were studied. The Rb(Ⅰ) spectrum at 780.02 nm showed the isotopic features and hyperfine splittings. This work provides a key idea that the diode lasers are useful in the specrochemical analysis of the radioactive actinides that have a rich spectrum with transitions which can be easily reached with AlGaAs diode lasers. Also, this study shows that the diode lasers can be an important tool to find the spectroscopic parameters of actinides and rare earth elements which have not known.