• Nuclear Engineering and Technology
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• 제55권2호
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• pp.669-673
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• 2023

Introduction: The crucial step in preclinical process of radiopharmaceutical production is internal dosimetry evaluation by different ways to realize radiobiological dose-response relationships and to extract the results for clinical use. Till now several bone-seeking radiopharmaceuticals have been developed for bone metastasis. Interesting features of bisphosphonates attracted attentions to them in the field of radiopharmaceutical therapy and studies on new generation of them have been doing too. Materials and methods: In this study, we used ZNA as representative of the third generation. The radiopharmaceutical ¹⁸⁸Re-ZNA was produced and its radiochemical purity was investigated. Then, the biological distribution of the produced radiopharmaceutical at 1, 2, 4 and 24 h after injection on different organs of mice were investigated. Finally, the absorbed dose of organs in the human body was assessed using the RADAR method. Results: The results show 96% radiochemical purity of the ¹⁸⁸Re-ZNA radiopharmaceutical. The amount of %ID/g in bone is 1.131% after 1 h and in 24 h it has a significant amount compared to other organs, that is 0.516%. Also dosimetric results show that the highest absorption dose is related to bone and the amount of this dose is 0.050 mGy/MBq. Conclusion: Considering the possibility of producing the ¹⁸⁸Re-ZNA radiopharmaceutical, as well as the proper distribution of this radiopharmaceutical in target and non-target organs and increasing the absorbed dose in bone, it can be concluded that this radiopharmaceutical can be useful in the "radiopharmaceutical therapy" in metastases.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.923-924
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• 2005

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1526-1531
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• 2024

¹³¹I is a fission product produced in a nuclear reactor by irradiating tellurium dioxide, with a half-life of 8.02 day. The most important and widely used method for making ¹³¹I is irradiation using a nuclear reactor and post-irradiation followed by dry distillation. The advantage of the dry distillation process is that the process and the equipment are relatively simple, namely TeO₂ (m.p. 750 ℃), which can withstand heating during reactor irradiation. Based on TeO₂ irradiation by neutron following the technique of dry distillation was explained for production of ¹³¹I on a large scale. A dry distillation followed the radioisotope production operation using the 30 MW GA Siwabessy nuclear reactor to meet national demand. TeO₂ targets are 25 and 50 g irradiated for 87-100 h. The resulting ¹³¹I activity is 20.29339-368.50335GBq. According to the requirements imposed on the radionuclide purity of the preparation, the contribution of ¹³¹I training in the resulting preparation was not less than 99.9 %

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.1064-1065
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• 2005

• 한국진공학회:학술대회논문집
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• 한국진공학회 2012년도 제43회 하계 정기 학술대회 초록집
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• pp.262-262
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• 2012

A multi-purpose cyclotron, MC50 has been operated to provide multi-ions of proton, deuteron and alpha at Korea Institute of Radiological and Medical Sciences (KIRAMS). Neutron is also produced through the (p,n) nuclear process with a Be target. However, a wide spectrum of current of ions is requested by beam users for carrying their various application fields. Therefore a simulation study is requested on the design of an axial injection system for high current proton and alpha beam extraction for radio-isotope productions and scientific researches. The purpose of this study is seeking a relatively simple method for the MC50 having higher alpha beam capability and also improving proton and deuteron beams currently used. We are considering two possibilities to improve the internal ion source and to install a new external axial injection system. The external injection system will be consisted of an Einzel lens, a steering magnet, a buncher, and a glazer lens placed in front of an inflector, which is located at the center of the main magnet.

• 대한방사성의약품학회지
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• 제8권2호
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• pp.87-93
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• 2022

[¹⁸F]FDG is known as the most widely used radiopharmaceutical in the imaging field of nuclear medicine worldwide. With the introduction of PET equipment, the demand for [¹⁸F]FDG has increased and the production volume has also increased. However, in order to increase production, the use of ¹⁸F radioisotope must be increased or [¹⁸F]FDG must be synthesized in high yield. Therefore, in order to meet the high yield and purity of radiopharmaceuticals, a radiopharmaceutical automatic synthesizer was required. As the use of [¹⁸F]FDG increased, automated synthesizer manufacturers supplied various types of radiopharmaceutical automated synthesizers to the market. In this study, we developed a commercialized [¹⁸F]FDG radiopharmaceutical automatic synthesizer (sCUBE FDG) using a disposable cassette type that complies with GMP developed by FutureChem, a leading radiopharmaceutical company. We used sCUBE FDG to verify the production process, radiopharmaceutical's quality (radiochemical purity, etc.), and radiochemical yield of [¹⁸F]FDG. As a result of optimizing the automatic synthesis process and synthesizing a total of 30 times, the production time was 35 ± 3 minutes and the average production yield was 65.6%.

• 산업공학
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• 제24권3호
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• pp.187-195
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• 2011

The automatic radiopharmaceutical module consists of several 2-way valves, couple of syringes, gas supply unit, heating(cooling) unit and sensors to control the chemical reagents as well as to help the chemical reaction. In order to control the actuators of radiopharmaceutical module, the process is tabulated using spread sheet as like excel. Unlike the common program, a trivial error is too critical to allowed in the process because the error can lead to leak the radioactive reagent and to cause the synthesis equipment failure during synthesizing. Hence, the synthesis process has been validated using graphic simulation while the operator checks the whole process visually and undergoes trial and error. The verification of the synthesis process takes a long time and has a difficulty in finding the error. This study presents a methodology to verify the process algebraically while the radiopharmaceutical module is converted to the network model. The proposed method is validated using actual synthesis process.

• 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.

• 한국방사선학회논문지
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• 제7권6호
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• pp.397-402
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• 2013

우리나라 약사법과 외국의 방사성의약품 제조관리기준 가이드라인을 참고하여 방사성의약품 제조관리기준 제정 시 고려해야할 사항들에 대해 의견을 제시하였다. 의약품은 안전성, 유효성과 더불어 제품의 균일성이 검증되어야 한다. 따라서 방사성의약품의 특성을 충분히 고려한 합리적인 제조관리기준을 제정하면 방사성의약품 관리의 효율성을 증대시키고 국민건강 증진에 기여할 수 있을 것으로 기대된다.

• Bulletin of the Korean Chemical Society
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• 제31권11호
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• pp.3309-3312
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• 2010

D-[$^{18}F$]FMAU and L-[$^{18}F$]FMAU are F-18 labeled nucleoside analogue which have been efficiently synthesized in order to be a PET imaging probe. D-[$^{18}F$]FMAU and L-[$^{18}F$]FMAU were compared as PET imaging agents using HSV1-TK gene expressing tumor-bearing mice. Their cellular uptake profiles were also compared using MCA and MCA-TK cell lines. D-[$^{18}F$]FMAU demonstrated higher cellular uptake and higher accumulation in MCA-TK tumor regions than L-[$^{18}F$]FMAU. On the other hand, L-[$^{18}F$]FMAU showed higher MCA-TK/MCA ratio of %ID/g than that of D-[$^{18}F$]FMAU. L-[$^{18}F$]FMAU can be utilized as a good candidate for HSV1-TK PET imaging. It can be used for antiviral drug evaluation.