• 한국콘텐츠학회논문지
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• 제9권11호
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• pp.240-246
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• 2009

본 연구의 목적은 방사성 의약품의 정도관리 실험 중 방사선 및 의약품측면에서의 방사핵종 순도, 화학적 순도, 방사화학적 순도의 세 가지로 진행하였다. 또한 방사성 의약품을 표지 후 시간에 따른 표지 효율을 관찰함으로써 실제 임상에서 표지 후 어느 정도의 시간이 경과해도 사용이 가능한지 실험해 보았다. 그 결과 현재 임상에서 사용되고 있는 방사성의약품의 방사성핵종 순도와 화학적 순도는 양호한 편이었으나, 방사화학적 순도는 표지방법과 표지 시간에 따라 약간의 차이를 띄고 있었다. 방사성 의약품은 시술자의 손을 거쳐 표지되기 때문에 표지과정에 주의를 하여 정도관리에 임한다면 보다 효율적인 검사가 가능할 것으로 보여 진다.

• 대한화학회지
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• 제9권2호
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• pp.96-100
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• 1965

우리나라 硏究用 原子爐 TRIGA Mark Ⅱ에 依한 無擔體의 Fe-59를 製造할 目的으로 分離法과 放射化學的 純度 및 核反應斷面積을 檢討하였다. 分離된 Fe-59를 ${\gamma}$-ray spectrometry와 半減期測定에 依하여 純度를 定한 結果 99.9%以上이었다.

• Bulletin of the Korean Chemical Society
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• 제32권6호
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• pp.1931-1935
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• 2011

The synthesis of carbocyclic analogues of normal nucleosides has grown exclusively since they have shown potential antiviral and antitumor activities. Radiolabeled cis-1-[4-(hydroxy-methyl)-cyclopent-2-enyl]-5-$[^{124}I]$-iodocytosine (carbocyclic d4IC) and cis-1-[4-(hydroxy-methyl)-cyclopent-2-enyl]-5-(2-$[^{124}I]$iodovinyl)cytosine(carbocyclic d4IVC) were synthesized. The synthetic route employed Pd(0)-catalyzed coupling reaction together with organotin and exchange reaction for radioiodination as key reactions. Carbocyclic $[^{124}I]$d4IC gave more than 75% radiochemical yield with greater than 95% radiochemical purity. Carbocyclic $[^{124}I]$d4IVC gave more than 80% radiochemical yield with greater than 95% radiochemical purity.

• 대한방사성의약품학회지
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• 제3권1호
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• pp.44-51
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• 2017

Herein we report an efficient radiolabeling method based on a rapid condensation reaction between N-terminal cysteine and 2-cyanobenzothiazole (CBT). Radioiodination of 2-cyano-6-hydroxybenzothiazole 2 was carried out using chloramine-T to give $^{125}I$-labeled CBT ([$^{125}I$]1) with a high radiochemical yield ($90{\pm}6%$ isolated yield, n=3) and radiochemical purity (>99%). To evaluate the radiolabeling efficiency of $^{125}I$-labeled CBT, model compounds, L-cysteine and N-terminal cysteine conjugated cRGD peptide were reacted with [$^{125}I$]1 under mild conditions. The radiolabeling reactions rapidly provided the $^{125}I$-labeled products [$^{125}I$]5 and [$^{125}I$]6 with excellent radiochemical yields and radiochemical purity. Therefore, we demonstrate that [$^{125}I$]1 will be a useful prosthetic group for radioactive iodine labeling of N-terminal cysteine bearing biomolecules.

• 대한방사성의약품학회지
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• 제2권1호
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• pp.43-50
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• 2016

$^{89}Zr$ with the favorable nuclear decay kinetics and chemical properties is an appealing radiometal for its application in immuno-PET using radiolabeled monoclonal antibodies. Rising demand of ultrahigh purity and high-specific activity $^{89}Zr$ has propelled the radiochemist worldwide to develop an overall efficacious method for its promising separation from the target matrix $^{89}Y$. The requirement of elevated radiochemical purity (${\geq}$ 99.99%) has accelerated the efforts since last two decades to achieve higher decontamination and separation factors of carrier free $^{89}Zr$ over $^{89}Y$ using several suitable separation techniques. However, each of the technique has its own pros and cons which prior to its actual medical application needs to be optimized and thoroughly scrutinized to avoid further complications during radiolabelling of the pharmaceuticals. In this short review article we will specifically consider as well focus on the historical development and the recent advances on the radiochemical separation of $^{89}Zr$ from $^{89}Y$ which will be helpful for the separation scientist involved in this area to understand the existing available means and plan the strategy to investigate and develop the novel techniques to overcome the problems involved in the present methods.

• 대한방사성의약품학회지
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• 제2권2호
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• pp.132-136
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• 2016

Radiolysis is the process of decreasing in Radio-Chemical Purity (RCP) of [$^{18}F$]FDG by direct effect and indirect effect of self Radio-activity. The objective of our study was to figure out the ideal conditions which minimize damages of quality of [$^{18}F$]FDG using radical scavenger and controlling temperature of storage.

• 대한방사성의약품학회지
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• 제7권2호
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• pp.147-152
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• 2021

C-11 Radiolabeled amino acid-based radiopharmaceuticals such as [¹¹C]MET for brain tumor PET imaging have limitations due to their short half-life (20 min). F-18 radiolabeled amino acid derivatives have been developed to overcome for the short half-life, one of which is [¹⁸F]FET. Brain tumor imaging using [¹⁸F]FET showed high uptake in tumor region and no non-specific uptake in inflammatory tissue, which was useful in discriminating the difference between inflammation and tumor especially. In this study, [¹⁸F]FET was synthesized using an automatic synthesis module and quality tests were carried out including enantiomeric purity analysis with reference compounds. Radiochemical yield was 50.3 ± 4.9% (n=7, decay-corrected) with molar activity of 76 ± 17 GBq/mmol. The radiochemical purity of >99%. Enantiomeric purity of [¹⁸F]FET using chiral HPLC analysis showed >99%, which was confirmed by co-injection with the L-FET and D-FET authentic standards. [¹⁸F]FET was prepared with high radiochemical yield and molar activity including no racemate mixture.

• 대한핵의학회지
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• 제24권1호
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• pp.101-107
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• 1990

To develop $^{131}I-labelled$ m-iodobeneylguanidine $(^{131}I-MIBG)$, various experiments such as synthesis of MIBG, establishment of labelling conditions, determination of radiochemical purity, and examination of stability were carried out. 1) m-Iodobenzylguanidine (MIBG) sulfate was synthesized with a total yield of 62.4% by the condensation of m-iodobenzylamine hydrochloride with cyanamide via MIBG bicarbonate. Its physical properties, IR, $^1H-NMR$, and elemental analysis data were nearly identical to those of literature. 2) Freeze-dried or vacuum-dried kit vials were prepared from the mixture so as to contain MIBG (2 mg), ascorbic acid (10 mg), copper (II) sulfate (0.14 mg), and tin (II) sulfate (0.5 mg) per vial. Copper ( I ) catalyzed radioiodination of MIBG was carried out using kit vials and 0.01 M $H_2SO_4$ as solvent at $100^{\circ}C$ for 30 min under nitrogen atmosphere (optimal conditions). Labelling yield was 98% and radiochemical purity was 99.5%, respectively. 3) Solid-phase radioiodination of MIBG was carried out at $155^{\circ}C$ for 30 min using the prepared vials to contain MIBG (2 mg) and ammonium sulfate (10 mg). Duplicate reactions under the same conditions showed labelling yield of 95% and radiochemical purity of 99.5%. 4) $^{131}I-MIBG$ prepared either by catalytic or by solid-phase exchange method showed radio-chemical purity of 99% even after 3 days storing at room temperature.

• 핵의학기술
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• 제16권1호
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• pp.8-11
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• 2012

상용화된 자동합성장치는 사용되는 유기용매의 종류가 다르고 합성수율에 차이를 보인다. 따라서 본 연구에서는 자동합성장치에 따른 $^{18}F$-FDG의 방사선분해에 관한 방사화학적순도 변화를 비교하였다. Cyclotron (PETtrace, GE Healthcare)을 사용하여 $^{18}F$를 생산하고, 자동합성장치(FASTlab, Tracerlab MX, GE Healthcare)를 이용하여 FDG로 합성하였다. 방사화화적순도는 Radio-TLC Scanner (AR 2000, Bioscan), GC(Gas Chromatography, Agilent 7890A)를 사용하여 $^{18}F$-FDG에 함유되어 있는 에탄올의 양을 측정하였다. 고정상은 실리카겔로 도포된 유리판($1{\times}10cm$), 이동상은 아세토니트릴과 물 19:1 혼합액을 사용하고, 각각의 합성장치에서 고농도와 저농도의 $^{18}F$-FDG를 생산 후 2시간 간격으로 방사화학적순도를 측정하였다. 저농도 (약 2.59 GBq/mL 이하)에서 순도변화는 Tracerlab MX에서는 99.26%, 98.69%, 98.25%, 98.09%, FASTlab에서는 99.09%, 97.83, 96.89%, 96.62%를 얻었다. 고농도(약 3.7 GBq/mL 이상)에서 순도변화는 Tracerlab MX에서는 평균 99.54%, 96.08%, 93.77%, 92.54%, FASTlab의 경우 99.53%, 95.65%, 92.39%, 89.82%를 얻었다. 그리고 FASTlab에서 생산한 $^{18}F$-FDG의 GC에서는 에탄올이 검출되지 않았으며, Tracerlab MX에서는 100~300 ppm의 에탄올이 검출되었다. 이러한 결과를 비추어 봤을 때 방사선 보호제인 에탄올의 유무보다 방사능농도가 방사선분해에 더 큰 영향을 미치기 때문에 고농도의 $^{18}F$-FDG 생산 후 무균 생리식염수로 희석하여 농도를 낮춘 후 사용해야 한다.

• 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.