• 대한방사성의약품학회지
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• 제2권2호
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• pp.84-95
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• 2016

Considerably increasing interest in using the theranostic isotopes/ isotope pairs of radiometals like $^{44/47}Sc$ and $^{64/67}Cu$ for diagnosis and/or therapeutic applications in the nuclear medicine procedures necessitates its reliable production and supply. Separation and purification of no-carrier-added (NCA) isotopes from macro quantitates of the irradiated target matrix along with other impurities is a cardinal procedure amongst several other steps involved in its production. Multitudinous methods including but not limited to liquid-liquid (solvent) extraction, extraction chromatography (EXC), ion exchange, electrodeposition and sublimation are routinely applied either solitarily or in combination for the separation and purification of radioisotopes depending on their production routes, radioisotope of interest and impurities involved. However, application of EXC though has shown promises towards the numerous separation techniques have not received much attention as far as its application prospects in the field of nuclear medicine are concerned. Advances in the recent past for application of the EXC resins in separation and purification of the several medically important radioisotopes at ultra-high purity have shown promising behavior with respect to their operation simplicity, acidic and radiolytic stability, separation efficiencies and speedy procedures with the enhanced and excellent extraction abilities. In this mini review we will be talking about the recent developments in the application and the use of EXC techniques for the separation and purification of $^{44/47}Sc$ and $^{64/67}Cu$ for medical applications. Furthermore, we will also discuss the scientific and practical aspects of EXC in the view of separation of the NCA trace amount of radionuclides.

• 대한방사선기술학회지:방사선기술과학
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• 제38권4호
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• pp.477-482
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• 2015

핵의학과에 근무하는 방사선작업종사자들은 방사성동위원소의 생산, 분배, 조제, 주입 등의 업무를 진행하며, 이러한 과정에서 손에 대한 방사선 피폭이 높게 발생한다. 이에 본 연구에서는 핵의학과에서 이용되는 방사성동위원소의 에너지로서 140 keV와 511 keV의 ${\gamma}$선에 대한 차폐효과를 몬테카를로 모의 모사를 통해 분석하였다. 모의실험 결과 140 keV ${\gamma}$선은 차폐체에 두께와 상관없이 모두 방사선에 대한 차폐효과가 발생되었으며, 511 keV의 ${\gamma}$선에서는 1.1 mm 이상에서 차폐효과가 발생되었다. 그러나 1.1 mm 미만에서는 2차적으로 발생된 산란선으로 인하여 차폐효과가 없었으며, 오히려 방사성동위원소의 피폭선량이 증가되었다. 따라서 효율적인 방사선 방어를 위해서는 핵종별 에너지에 따른 납 차폐체의 두께를 고려하여야 할 것이다.

• 대한방사선기술학회지:방사선기술과학
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• 제33권2호
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• pp.133-141
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• 2010

선형가속기의 동적쐐기(enhanced dynamic wedge: EDW)의 품질보증을 위하여 다양한 방법으로 동적쐐기의 특성을 평가하였다. 본 연구에서는 6 MV와 15 MV 엑스선에 대하여 각각 7종(10, 15, 20, 25, 30, 45, 60도)의 EDW를 평가하였다. EDW 작동에 필요한 STT(segmented treatment table)를 계산으로 구하고 로그파일을 통하여 기계적 작동을 평가하였으며, 이차원배열형검출기와 전리함을 사용하여 팬텀속 선량분포를 측정하고 치료계획시스템(RTP)과 비교하였다. EDW의 기계적 작동은 예상과 잘 일치하였으며, 빔측면도를 포함한 이차원선량분포는 근사적으로 RTP 계산과 일치하였다. 선형가속기 조사량 100 MU에 대한 출력선량은 RTP 계산과 2.9% 이내로 일치하였으며, 측정된 쐐기인자는 RTP 계산과 최대 2.6%를 보였다. 이 결과들은 본 선형가속기에 장착된 EDW의 임상적 적용에 문제가 없음을 의미한다.

• 방사선산업학회지
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• 제11권1호
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• pp.39-45
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• 2017

A cyclotron is a kind of particle accelerator that produces a beam of charged particles for the production of medical, industrial, and research radioisotopes. More than 30 cyclotrons are operated in Korea to produce $^{18}F$, an FDG synthesis at hospitals. A 30-MeV cyclotron was installed at ARTI (Advanced Radiation Technology Institute, KAERI) mainly for research regarding isotope production. In this study, we analyze and estimate the items of risk such as the problems in the main components of the cyclotron, the loss of radioactive materials, the leakage of coolant, and the malfunction of utilities, fires and earthquakes. To estimate the occurrence frequency in an accident risk assessment, five levels, i.e., Almost certain, Likely, Possible, Unlikely, and Rare, are applied. The accident consequence level is classified under four grades based on the annual permissible dose for radiation workers and the public in the nuclear safety law. The analysis of the accident effect is focused on the radioactive contamination caused by radioisotope leakage and radioactive material leakage of a ventilation filter due to a fire. To analyze the risks, Occupation Safety and Health Acts is applied. In addition, action plans against an accident were prepared after a deep discussion among relevant researchers. In this acts, we will search for hazard and introduce the risk assessment for the research 30-MeV cyclotron facilities of ARTI.

• 방사선산업학회지
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• 제11권1호
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• pp.19-25
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• 2017

It is suggested that the dose limit recommended in the Enforcement Decree of Korea's Nuclear Safety Act should not exceed 150 mSv per year for radiation workers. Recently, however, ICRP 118 report has suggested that the threshold dose of the lens should be reduced to 0.2~0.5 Gy and the mean dose should not exceed 50 mSv per year for an average of 20 mSv over 5 years. Based on these contents, $^{123}I$, $^{99m}Tc$, and $^{18}F-FDG$, which are radioisotope drugs that are used directly by radiation workers in the nuclear medicine department in Korea are expected to receive a large dose of radiation in the lens in distribution and injection jobs to administer them to patients. The ED3 Active Extremity Dosimeter was used to measure the dose of the lens in the nuclear medicine and radiation workers and how much of the dose was received per 1 mCi.

• Journal of Radiation Protection and Research
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• 제46권3호
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• pp.134-142
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• 2021

Background: From 2018 to 2020, the Expert Study on Public Understanding after the Fukushima Daiichi Nuclear Power Plant Accident (the Expert Study Group) identified and analyzed activities designed to promote public understanding of science and radiation since the Fukushima accident, and held discussions on how to achieve public understanding in the situation where public confidence has been lost, and how experts should prepare for dealing with the public. This panel session was held at the 53^rd meeting of the Japan Health Physics Society on June 30, 2020. Materials and Methods: First, three subgroup (SG) leaders reported their research methods and results. Then, two designated speakers, who participated as observers of the Expert Study Group, commented on the activities. Next, the five speakers held a panel discussion. Finally, the rapporteur summarized. Results and Discussion: SG leaders presented reports from researchers and practitioners in health physics and environmental risks who provided information after the Fukushima accident. During the discussion, experts in sociology and ethics discussed the issues, focusing on the overall goals of the three groups, local (personal) and mass communication, and ethical values. Many of the activities instituted by the experts after the accident were aimed at public understanding of science (that is, to provide knowledge to residents), but by taking into account interactions with residents and their ethical norms, the experts shifted to supporting the residents' decision-making through public engagement. The need to consider both content and channels is well known in the field of health communication, and overlaps with the above discussion. Conclusion: How to implement and promote the public engagement in society was discussed in both the floor and designated discussions. Cooperation between local communities and organizations that have already gained trust is also necessary in order to develop relationships with local residents in normal times, to establish an information transmission system, and to make it work effectively.

• Journal of Gastric Cancer
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• 제19권2호
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• pp.157-164
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• 2019

Purpose: Although standard radical gastrectomy is recommended after noncurative resection of endoscopic submucosal dissection (ESD) for early gastric cancer in most cases, residual tumor and lymph node metastasis have not been identified after surgery. The aim of this study is to evaluate the feasibility of sentinel node navigation surgery after noncurative ESD. Materials and Methods: This trial is an investigator-initiated, multicenter prospective phase II trial. Patients who underwent ESD for clinical stage T1N0M0 gastric cancer with noncurative resections were eligible. Qualified investigators who completed the prior phase III trial (SENORITA 1) are exclusively allowed to participate. In this study, 2 detection methods will be used: 1) intraoperative endoscopic submucosal injection of dual tracer, including radioisotope and indocyanine green (ICG) with sentinel basins detected using gamma-probe; 2) endoscopic injection of ICG, with sentinel basins detected using a fluorescence imaging system. Standard laparoscopic gastrectomy with lymphadenectomy will be performed. Sample size is calculated based on the inferior confidence interval of the detection rate of 95%, and the calculated accrual is 237 patients. The primary endpoint is detection rate, and the secondary endpoints are sensitivity and postoperative complications. Conclusions: This study is expected to clarify the feasibility of laparoscopic sentinel basin dissection after noncurative ESD. If the feasibility is demonstrated, a multicenter phase III trial will be initiated to compare laparoscopic sentinel node navigation surgery versus laparoscopic standard gastrectomy in early gastric cancer after endoscopic resection.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.176-189
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• 2019

This paper presents a feasibility study for producing the medical isotope $^{99m}Tc$ using the hazardous and currently wasted radioisotope $^{99}Tc$. This can be achieved with the nuclear resonance fluorescence (NRF) phenomenon, which has recently been made applicable due to high-intensity laser Compton scattering (LCS) photons. In this work, 21 NRF energy states of $^{99}Tc$ have been identified as potential contributors to the photo-production of $^{99m}Tc$ and their NRF cross-sections are evaluated by using the single particle estimate model and the ENSDF data library. The evaluated cross sections are scaled using known measurement data for improved accuracy. The maximum LCS photon energy is adjusted in a way to cover all the significant excited states that may contribute to $^{99m}Tc$ generation. An energy recovery LINAC system is considered as the LCS photon source and the LCS gamma spectrum is optimized by adjusting the electron energy to maximize $^{99m}Tc$ photo-production. The NRF reaction rate for $^{99m}Tc$ is first optimized without considering the photon attenuations such as photo-atomic interactions and self-shielding due to the NRF resonance itself. The change in energy spectrum and intensity due to the photo-atomic reactions has been quantified using the MCNP6 code and then the NRF self-shielding effect was considered to obtain the spectrums that include all the attenuation factors. Simulations show that when a $^{99}Tc$ target is irradiated at an intensity of the order $10^{17}{\gamma}/s$ for 30 h, 2.01 Ci of $^{99m}Tc$ can be produced.

• 한국콘텐츠학회논문지
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• 제14권6호
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• pp.255-261
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• 2014

의료현장에서의 방사성폐기물은 방사성동위원소의 사용량의 증가와 더불어 급격히 늘어나고 있다. 특히, 갑상선 질병의 진단 및 치료용으로 사용량이 증가하고 있는 I-131 핵종의 경우 8.02 일의 짧은 반감기를 가지고 있으며, 관련 폐기물은 모두 자체처분 방법으로 처분하고 있다. 이와 관련하여 국제원자력기구(IAEA)는 개인선량(10 ${\mu}Sv/y$) 및 집단선량(1 man-Sv/y)과 핵종별 농도에 근거하여 각각 폐기물의 규제해제기준을 제시(IAEA Safety Series No 111-P-1.1, 1992 및 IAEA RS-G-1.7, 2004)하였다. 이 연구에서는 의료현장에서 발생하는 I-131 핵종 관련 폐기물을 사용상 종류별로 수집 및 측정하여 방사능농도의 측정 방법 및 절차를 수립한다. 또한, 측정 결과를 바탕으로 핵종의 감쇠 유도식을 산출하고, 이것을 바탕으로 자체처분 가능일자를 산출하여 이론식의 경우와 대비하여 고찰하였다. 측정 결과를 바탕으로 유도 감쇠식을 신정하여 이론적 반감기와 유효 반감기를 비교해 본 결과, I-131 핵종의 이론적 반감기가 유효반감기(7.72일)에 비해 긴 반감기를 가지고 있음을 확인하였다. 측정결과를 바탕으로 한 유효 반감기를 적용한다면, 현재보다 더 짧은 기간 동안 I-131 핵종 폐기물을 보관하였다가 자체처분을 할 수 있다. 이 연구 결과는 ISO 표준으로 추진할 예정이다.

• 한국의학물리학회지:의학물리
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• 제10권3호
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• pp.151-157
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• 1999

심장 혈관 협착증 환자의 경우 수술후 재협착을 방지하기 위하여 혈관내 방사선 조사를 실시하여 혈관내벽의 세포증식을 억제하는 방법이 시도되고 있다. 이를 위해 여러 가지 방사성 동위원소가 사용되고 있지만 한국원자력연구소에서 생산되는 Ho-166 도 그 중의 하나의 원소이다. 따라서 이 Ho-166 을 이용하여 혈관내 방사선조사를 할 경우 선량분포를 측정해 보았다. 혈관 내벽을 방사선 조사하는 방법은 풍선 혈관 카테터를 혈관내에 위치시키고 풍선 안에 액체 상태인 Ho-l66 동위원소를 채우고 일정시간 머물게 함으로써 시행된다. 선량분포를 측정하기 위하여 Solid water phantom 과 방사선 흡수선량에 따라 현상기에 현상을 하지 않아도 바로 필름 흑화도 변화를 볼 수 있는 GafChromic Film 을 사용하였다. 필름 흑화도 측정은 Videodensitometer를 이용하였으며 Co-60 빔에 검교정된 GafChromic 필름의 흑화도로 부터 풍선 혈관 카테터 안에 있는 Ho-166 동위원소에 의한 선량분포플 측정하였다. 먼저 Co-60 빔을 이용한 GafChromic Film 의 calibration curve를 얻었다. 흡수선량 대 필름 흑화도 곡선 (H-D curve)은 직선을 이루지 않았으며 이는 densitometer에 쓰이는 광원으로 부터 짐작되는 결과이다. H-D 곡선을 이용하여 Ho-l66이 채워진 풍선 혈관 카테터로 부터의 거리에 따른 선량분포를 얻었으며 카테터 표면으로 부터 1 mm 떨어진 거리에서의 선량은 풍선 표면에서의 약 20% 정도 였으며 5mm 떨어진 거리에서는 풍선 표면 선량의 약 1% 정도로 급속히 떨어짐을 볼 수 있었다. 혈관내 방사선 조사시 중요한 것은 혈관 내 벽에는 원하는 만큼의 방사선량을 주어야 하지만 주변의 정상조직에는 최소한의 손상을 유지해야 하므로 선량분포가 동위원소로 부터 떨어졌을 때 급속히 감소해야 한다는 것이다 따라서 이와같은 이유 때문에 베타선 방출 핵종 들이 많이 시도되고 있으며 동위원소 Ho-l66 도 혈관내벽 방사선조사를 위한 하나의 좋은 핵종으로 이용할 수 있다.