• 한국융합학회논문지
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• 제11권8호
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• pp.71-76
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• 2020

본 연구는 병원 내 일반 공용화장실과 핵의학 전용화장실내의 방사성 표면오염도를 측정하였다. 측정방법은 Berthold(LB 124, Germany)을 이용하여 화장실 입구, 대변기 안, 대변기 주위바닥, 소변기 안, 소변기 주위바닥에서 측정하였다. 화장실 사용실태 결과 3곳의 병원 중 1곳의 병원에서 방사성동위원소를 투여 받은 환자가 대기하는 전용장소가 없었다. 방사성동위원소 전용 화장실을 측정한 결과 방사성옥소 치료병실에서 모든 측정 장소가 가장 높게 측정되었고, 공용화장실을 측정한 결과는 B병원을 제외한 모든 병원의 측정 장소에서 백그라운드 수준의 오염도를 나타냈다. 하지만 B병원의 1층 공용화장실 소변기 안, 소변기 주위바닥에서 8.073 Bq/㎠, 6.426 Bq/㎠으로 측정되었다. 따라서 환자들에게 방사선피폭의 위험성을 설명하고, 환자가 대기할 수 있는 장소를 마련할 것을 권고 한다. 그리고 방사성동위원소를 투여 받은 환자는 불필요한 이동과 일반 공용화장실을 사용하지 못하도록 하는 방안이 모색되어야 할 것이다.

• 대한방사선기술학회지:방사선기술과학
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• 제28권2호
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• pp.79-89
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• 2005

본 연구는 방사성동위원소 및 방사선 응용 분야에 있어서 우리나라가 연구개발 사업을 추진하는 데 도움이 될 수 있도록 국제원자력기구(IAEA) 프로그램의 현황을 검토하고 향후 전망을 제시하였다. 특히 국제기구를 통한 공동연구 프로그램 참여를 증진시킬 수 있도록 IAEA 프로그램 참여시 이점을 고찰하고 이의 필요성을 강조하였다. 또한 신규 참여 증진을 위한 방향을 제시하고 이의 효율적인 운영 방안을 제안하였다. 본 논문에서 제시된 전략과 구체적인 방안이 향후 국제공동연구 확대를 위한 정책 수립에 활용되고, 방사선기술 응용 연구를 수행하는 국내 산 학 연 연구기관의 국제공동연구 참여 증진에 기여할 수 있기를 기대한다.

• 방사선산업학회지
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• 제11권1호
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• pp.47-54
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• 2017

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a significant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity.

• Nuclear Engineering and Technology
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• 제47권7호
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• pp.875-883
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• 2015

The use of subcritical aqueous homogenous reactors driven by accelerators presents an attractive alternative for producing $^{99}Mo$. In this method, the medical isotope production system itself is used to extract $^{99}Mo$ or other radioisotopes so that there is no need to irradiate common targets. In addition, it can operate at much lower power compared to a traditional reactor to produce the same amount of $^{99}Mo$ by irradiating targets. In this study, the neutronic performance and $^{99}Mo$, $^{89}Sr$, and $^{131}I$ production capacity of a subcritical aqueous homogenous reactor fueled with low-enriched uranyl nitrate was evaluated using the MCNPX code. A proton accelerator with a maximum 30-MeV accelerating power was used to run the subcritical core. The computational results indicate a good potential for the modeled system to produce the radioisotopes under completely safe conditions because of the high negative reactivity coefficients of the modeled core. The results show that application of an optimized beam window material can increase the fission power of the aqueous nitrate fuel up to 80%. This accelerator-based procedure using low enriched uranium nitrate fuel to produce radioisotopes presents a potentially competitive alternative in comparison with the reactor-based or other accelerator-based methods. This system produces ~1,500 Ci/wk (~325 6-day Ci) of $^{99}Mo$ at the end of a cycle.

• Journal of Ginseng Research
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• 제47권1호
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• pp.74-80
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• 2023

Background: Although many studies have evaluated the efficacy and pharmacokinetics of Korean Red Ginseng (KRG) components (Rg1, Rb1, Rg3, Rd, etc.), few have examined the in vivo pharmacokinetics of the radiolabeled components. This study investigated the pharmacokinetics of ginsenosides and their metabolite compound K (CK), 20(s)-protopanaxadiol (PPD), and 20(s)-protopanaxatriol (PPT) using radioisotopes in rat oral administration. Methods: Sprague-Dawley rats were dosed orally once with 10 mg/kg of the tritium(3H) radiolabeled samples, and then the blood was collected from the tail vein after 0.25, 0.5, 1, 1.5, 2, 4, 6, 8, 12, 24, 48, 96, and 168 h. Radioactivity in the organs, feces, urine, and carcass was determined using a liquid scintillation counter (LSC) and a bio-imaging analyzer system (BAS). Results and conclusion: After oral administration, as the ³H-labeled ginsenosides were converted to metabolites, C_max and half-life increased, and T_max decreased. Interestingly, Rb1 and CK showed similar values, and after a single oral administration of components, the cumulative excretion ratio of urine and feces was 88.9%-92.4%. Although most KRG components were excreted within 96-168 h of administration, small amounts of components were detected in almost all tissues and mainly distributed to the liver except for the digestive tract when observed through autoradiography. This study demonstrated that KRG components were distributed to various organs in the rats. Further studies could be conducted to prove the bioavailability and transmission of KRG components to confirm the mechanism of KRG efficacy.

• 대한방사성의약품학회지
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• 제9권1호
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• pp.23-33
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• 2023

Prostate cancer ranks as the world's second most frequently diagnosed cancer among men, and is responsible for the fifth highest number of cancer-related deaths in this population. The development of effective diagnostic and therapeutic approaches for prostate cancer remains a major challenge in the field of oncology. Over the past few years, the prostate-specific membrane antigen (PSMA) has raised as a hopeful tracer for the diagnosis and treatment of prostate cancer.Various radioisotopes, such as ¹³¹I, ^99mTc, ⁶⁸Ga, and ¹⁷⁷Lu, have been used to label PSMA analogues, with varying degrees of success. Among these, ⁶⁸Ga-PSMA-11 and ¹⁷⁷Lu-PSMA-617 have emerged as the most promising radioligands for clinical use. Recently, researchers have been exploring the use of other radioisotopes, such as ²¹¹At, ⁸⁹Zr, ^64/67Cu, and ^203/212Pb, for the labeling of PSMA-targeted radioligands. These radioisotopes have unique properties that may offer advantages over existing radioligands, such as longer half-lives, higher specific activities, and different emission profiles. Efforts are currently underway to develop these radiopharmaceuticals and make them more widely available for clinical use. These exciting developments highlight the potential of PSMA-targeted radioligands for the diagnosis and treatment of prostate cancer, and provided significant implications for the management of this disease in the future. The current study aims to provide a comprehensive summary of the latest research and clinical applications of radiolabeled PSMA inhibitors for diagnoses and therapy of prostate cancer, emphasizing the exciting developments in the field and their potential impact on clinical practice.

• 대한핵의학회지
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• 제30권3호
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• pp.351-360
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• 1996

새로운 내부 방사선 치료용(Internal radiotherapy) $^{166}Ho$-CHICO와 CHIMA를 개발하고자 한다. $^{166}Ho$-CHICO 형성에 pH, 반응시간, chitosan 농도, $^{166}Ho$의 양 등의 영향을 실험하고, 형성된 $^{166}Ho$-CHICO로부터 $^{166}Ho$-CHIMA를 제조하여 $^{166}Ho$-CHICO와 CHIMA의 체내외 안정성 검사 등의 실험을 수행하였다. $^{166}Ho$-CHICO 형성시 최적의 조건은 pH 3.0에서 0.75% 이상의 chitosan 용액과, chitosan 무게에 대해 최대 20%까지는 $^{166}Ho$이 정량적으로 착물을 형성하였고, $^{166}Ho$-CHICO를 알칼리 처리하여 $^{166}Ho$ CHIMA를 제조하였다. 그리고 $^{166}Ho$-CHICO와 CHIMA는 체내외에서 매우 안정하였다. $^{166}Ho$-CHICO와 CHIMA는 매우 이상적인 carrier로서의 특성을 지닌 천연의 chitosan에 $^{166}Ho$을 쉽게 정량적으로 표지할 수 있고, 높은 체내외 안정성으로 미루어보아 내부 방사선 치료용 제제로서의 이용 가능성이 매우 높으며, 앞으로 충분한 동물실험을 거치면 신규 내부 방사선 치료제로서 새로운 장을 열 수 있을 것이다.

• 대한핵의학회:학술대회논문집
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• 대한핵의학회 1967년도 제6회 학술대회
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• pp.102.2-102.2
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• 1967

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.761-762
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• 2005

• 대한방사선기술학회지:방사선기술과학
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• 제41권2호
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• pp.135-140
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• 2018

In this study, the dose of antimony shielding sheet was measured and the shielding rates according to the distance between the radioisotopes and the detector was analyzed according to the type of $^{99m}Tc$, $^{18}F$, $^{201}Tl$, $^{131}I$, $^{123}I$ using the antimony shielding sheet. The detector was used with an inspector. Six sheets of 0.25 mmPb were prepared with 20 cm width and length. Measurement results using $^{99m}Tc$, $^{201}Tl$, and $^{123}I$ showed that as the thickness of the sheet became thicker, the farther the distance from the source to the sheet was, the smaller the transmitted dose amount was measured. It was analyzed that a thickness of 1.50 mm or more was required to obtain a shielding rates of 90% or more. In the experiments of $^{18}F$ and $^{131}I$, the dose value was highest when 0.25 mm sheet was used, and the shielding rates was negative, unlike the results of other radioisotopes. Since $^{201}Tl$ are used when using antimony sheet and $^{18}F$ and $^{131}I$ have no shielding effect, it is thought that it is effective to reduce dose by repeating training and simulation training so that work can be done in a short time.