• Nuclear Engineering and Technology
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• 제5권3호
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• pp.234-239
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• 1973

페이퍼 크로마토그래피에 의한 o-iodohippuric acid-$^{131}$ I와 o-iodobenzoic acid-$^{131}$ I의 분리에 관한 기보된 방법은 착오인 것으로 밝혀졌다. 이들 두 유사 화합물들의 효과적 분리를 위하여 제시된 용매는 균일하게 섞여지지 않을뿐 아니라 그대로 사용하더라도 이들 두 화합물은 분리되지 않았다. o-iodohippuric acid-$^{131}$ I의 동위원소 교환법에 의한 제조과정에서 o-iodohippuric acid가 o-iodobenzoic acid로 변환되지 알음을 확인하였으며 Hippuran-$^{131}$ I의 방사화학적 순도 결정을 위한 간편한 방법을 제시하였다.

• 한국수소및신에너지학회논문집
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• 제34권1호
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• pp.83-89
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• 2023

In this study, a computer simulation work has been performed for the separation of electronic grade highly pure carbon dioxide more than 7 N purity through a cryogenic distillation process. For the cold utility as a cooling medium for a condenser of the cryogenic distillation column, propylene was utilized as a refrigerant in the vapor-recompression refrigeration cycle. Through this work, it was concluded that the cryogenic distillation column with two stage compression and refrigeration cycle were essential to obtain a highly-pure liquefied CO₂.

• 한국수소및신에너지학회논문집
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• 제16권3호
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• pp.244-252
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• 2005

It is very interesting and important in the academic point of view and in practical use the hydrogen-induced phase separation(HIPS) which appears during hydrogen heat treatment. Since hydrogen can be removed very fast by pumping it out the hydrogen-induced new lattice phase which can not be obtained without hydrogen can be preserved as meta-stable state. In this study it has been investigated whether the HIPS appear in Pd-Al, Pd-Co, Pd-Cr, Pd-Ti, Pd-V and Pd-Zr alloys and discussed thermodynamic representation of the HIPS. The Pd alloys were arc-melted under argon atmosphere and remelted 4 or 5 times for homogenization. The alloys were annealed at 600$^{\circ}C$ under vacuum for 24 hrs and then subjected to pressure-composition isotherm measurements at 100$^{\circ}C$. The hydrogen heat treatment(HHT) of samples was carried out at 600$^{\circ}C$ under hydrogen pressure of 70 bar for 6 days and PC isotherms at 100$^{\circ}C$ were measured. By comparing the PC isotherms measured before and after HHT, occurrence of phase separation was determined. The experimental results showed that the HIPS appeared only in Pd-0.05Co alloy. For Pd-Co alloys with various composition the PC isotherms were measured. By adopting Park-Flanagan model for ternary thermodynamics the Gibbs free energy change for Pd-Co-H solid solution was calculated and subsequently with this the HIPS in Pd-Co alloy was explained fairly.

• Journal of Radiation Protection and Research
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• 제20권1호
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• pp.1-7
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• 1995

스트론튬선택성을 갖는 크로마토그래피용 수지인 $Sr-Spec^{TM}$을 이용한 환경시료중 토양시료와 물시료에 대한 방사성 스트론들 분리를 고찰하였다. 이 수지는 질산수용액에서 스트론튬과 큰 결합능력을 가졌으며, 다량의 칼슘원소의 존재에서도 스트론튬분리를 할 수 있는 선택성을 가졌다. 그러나 K나 Ba와 같은 방해원소에 의해서는 스트론튬 추출능력이 감소하였고, 때문에 토양시료중의 스트론튬 분석시에는 이러한 방해원소의 제거단계가 필요하였다. 그러나 물시료증 스트론튬분석에서는 이 수지를 사용함으로써 간편하고 효율높게 분리할 수 있었다.

• Korean Chemical Engineering Research
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• 제43권5호
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• pp.588-594
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• 2005

흡착식 경유 탈황을 위하여 Y 제올라이트와 활성탄에서의 황화합물 흡착특성을 분석하였다. n-옥탄에 BT, DBT, 4,6-DMDBT가 각각 50 ppmw씩 포함된 모사경유와 상용경유를 이용한 회분식 흡착에서 금속이온($Cu^{2+}$, $Ni^{2+}$)이 교환된 제올라이트 흡착제들이 모사경유에서는 우수한 황화합물 흡착성을 보였으나 상용경유에서는 활성탄이 더 우수한 흡착능력을 나타냈다. 모사경유에 벤젠을 첨가하였을 때, 벤젠의 함량이 증가할수록 Ni-Y 제올라이트에서의 황흡착량은 급감하였는데, 활성탄에서는 황흡착량에 큰 영향을 받지 않았다. 활성탄에서의 파과실험에서 황화합물의 평형흡착이 일어나도록 상용경유를 최적 조건의 유속으로 주입하였을 때에 활성탄 1g은 황농도 186 ppmw인 상용경유를 15 ml까지 처리할 수 있었다. 다양한 용매를 이용한 활성탄 재생실험에서 톨루엔이 가장 우수한 재생능력을 나타냈다.

• 한국고분자학회:학술대회논문집
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• 한국고분자학회 2006년도 IUPAC International Symposium on Advanced Polymers for Emerging Technologies
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• pp.353-353
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• 2006

Deoxyribonucelic acid (DNA) molecules have a huge molecular weight so that DNA was reported to be a promising natural polymer to give durable films. Among many applications of DNA, the authors focused their attention on separation membranes derived from DNA because membranes will play an important role in environmental and energy related processes. DNA-polyion complex membranes were prepared from DNA and corresponding polycations. The DNA-polyion complex membranes showed chiral separation ability toward racemic amino acid mixtures.

• 방사성폐기물학회지
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• 제16권2호
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• pp.173-182
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• 2018

원자력 시설 내 방사능을 포함하는 물질의 제염을 위한 방법 중 거품제염은 2차폐기기물의 양을 저감시킬 수 있는 장점을 지니고 있다. 본 연구에서는 거품안정성을 증가시킬 수 있는 실리카 나노입자를 여러가지 조건을 달리하여 합성하였다. Cetyltrimethylammonium bromide(CTAB)는 거품제염제의 거품안정성에 많은 영향을 나타내었다. 이러한 거품안정성이 향상된 이유는 제염제 내에 공기와 용액간의 계면에서 실리카 나노입자와 계면활성제의 반응으로 생각된다. 또한, CTAB는 실리카나노입자의 분리특성에서도 우수한 성능을 나타냈었다. 실리카 나노입자 분리시, CTAB의 탄화수소기에 의한 소수성과 전하중성화에 의해서 실리카 나노입자의 응집현상을 향상시켰다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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• pp.83-83
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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. The solid cathode processing is necessary to separate the salt from the cathode since the uranium deposit in a solid cathode contains electrolyte salt. Distillation process was employed for the cathode processing. It is very important to increase the throughput of the salt separation system due to the high uranium content of spent nuclear fuel and high salt fraction of uranium dendrites. In this study, a mesh-covered crucible was investigated for the sat distillation of electrorefiner uranium deposits. A liquid salt separation step and a vacuum distillation step were combined for salt separation. The adhered salt in uranium deposits was efficiently removed in the mesh-covered crucible. The salt distiller was operated simply since repeated cooling - heating step was not necessary for the change of the crucible. The operation time could be reduced by the use of the mesh-covered crucible and the combined operation of the two steps. A method to preserve a vacuum level was proposed by double O-rings during the operation of the distiller with the mesh-covered crucible. After the salt distillation, the salt content was measured and was below 0.1wt% after the salt distillation. The residual salt after the salt distillation can be removed further during melting of uranium metal.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.812-818
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• 2024

The volume and toxicity of radioactive waste can be decreased by separating the components of high-level liquid waste according to their properties. An impregnated silica-based adsorbent was prepared in this study by combining N,N,N',N',N",N"-hexa-n-octylnitrilotriacetamide (HONTA) extractant, N',N'-di-n-hexyl-thiodiglycolamide (Crea) extractant, and macroporous silica polymer composite particles (SiO₂-P). The performance of platinum-group metals adsorption and separation on prepared (HONTA + Crea)/SiO₂-P adsorbent was then assessed together with that of co-existing metal ions by batch-adsorption and chromatographic separation studies. From the batch-adsorption experiment results, (HONTA + Crea)/SiO₂-P adsorbent showed high adsorption performance of Pd(II) owing to an affinity between Pd(II) and Crea extractant based on the Hard and Soft Acids and Bases theory. Additionally, significant adsorption performance was observed toward Zr(IV) and Mo(VI). Compared with studies using the Crea extractant, the high adsorption performance of Zr(IV) and Mo(VI) is attributed to the HONTA extractant. As revealed from the chromatographic experiment results, most of Pd(II) was recovered from the feed solution using 0.2 M thiourea in 0.1 M HNO₃. Additionally, the possibility of recovery of Zr(IV), Mo(VI), and Re(VII) was observed using the (HONTA + Crea)/SiO₂-P adsorbent.

• Bulletin of the Korean Chemical Society
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• 제33권8호
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• pp.2806-2808
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• 2012