• 대한임상독성학회지
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• 제9권2호
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• pp.39-48
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• 2011

In mass casualty situation due to radiological accidents, it is important to start aggressive management with rapid triage decisions. External contamination needs immediate decontamination and internal contamination should be treated with special expertise and equipment to prevent the rapid uptake of radionuclides by target organs. Acute radiation syndrome shows a sequence of events that varies with the severity of the exposure. More severe exposures generally lead to more rapid onset of symptoms and severe clinical findings. After the massive exposure, various systems of the body reflect their severe damages that can lead to death within hours or up to several months. The disease progression has classically been divided into four stages: prodromal, latent, manifest illness, and recovery or death. Three characteristic clusters of symptoms including the hematopoietic syndrome, the gastrointestinal syndrome and the cerebrovascular syndrome are all associated with the acute radiation syndrome. The standard medical management of the patients with a potentially survivable radiation exposure includes good medical, surgical and supportive measures. Specific treatment with cytokines and bone marrow transplantation should be considered. The management of internal contamination is much the same as the treatment of poisoning. The standard decontamination should be applied to reduce uptake, and the chelating agents can be administered to enhance the clearance of radioisotopes. Radioactive iodine ($^{131}I$) as one of the nuclear fission products can increase the incidence of thyroid cancer in children. Potential benefit of potassium iodide prophylaxis is greater especially in neonates, infants and small children.

• Journal of Radiation Protection and Research
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• 제36권2호
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• pp.99-106
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• 2011

원전에서 발생하는 방사성핵종 중에서 방사선작업종사자와 원전주변에 거주하는 일반인에 대한 피폭방사선량평가 측면에서 중요한 핵종 중에 하나가 삼중수소이다. 삼중수소는 인간의 체내로 섭취되어 내부피폭을 일으킨다. 원전 종사자 전체 피폭방사선량의 약 7%, 원전주변 일반인 피폭방사선량의 약 60-90%가 삼중수소에 의한 피폭으로 발생하고 있다. 이에 따라 국내외 연구소에서는 삼중수소에 대한 정확한 피폭방사선량 평가를 위해 많은 연구를 진행하고 있다. 본 논문은 삼중수소의 인체대사모델과 피폭방사선량 평가와 관련한 국내외 연구개발 동향을 정리하였고, 현안사항을 정리하였다.

• Journal of Radiation Protection and Research
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• 제38권4호
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• pp.234-236
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• 2013

비밀봉 방사성물질을 취급하는 시설에서 이들 물질에 의한 작업환경의 다소간의 오염은 피할 수 없다. 오염의 우려가 있는 작업환경에서 오염관리의 일차적인 목적은 방사성물질의 잠재적 체내섭취로 인한 영향이다. 본 논문은 보수적 가정과 간단한 계산에 의거하여 공기오염에 따른 방사성물질의 공기중 농도와 흡입에 의한 연간 섭취량을 산출한 후, 관련 고시에서 정하는 유도공기중농도와 연간섭취한도와 비교함으로써 종사자의 내부피폭 정도를 평가하는 절차를 제공한다. 제시된 절차는 공기중 방사성물질 측정 및 내부피폭 감시의 필요성, 적합한 방호용구의 착용, 배기설비 설계를 위한 정보 획득 등 공기오염과 종사자의 내부피폭 감시를 위한 실무적 요건을 판단할 목적으로 활용될 수 있다.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.155-159
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• 2001

Beta radiation is measured for an environmental monitoring purpose or for an internal radiation exposure monitoring of nuclear power plant's worker. In korea, strontium 89 and strontium 90 is measured for an environmental monitoring purpose. Also tritium and carbon 14 contained in urine is measured for an internal radiation exposure monitoring of nuclear power plant's worker. Because above isotopes emits low energy beta radiations having a wide range of energy, very complicated isotope separation preprocess is needed. In this study, two mixed beta emitting isotopes are measured simultaneously using a liquid scintillation counter(LSC) and analyzed by using a developed statistical method. Banded least square method is used to analyze the mixed spectrum, and the goodness-of-fitness test is proposed. Test results show that the developed procedure can be very useful for analyzing a mixed beta emitting isotopes.

• Journal of Radiation Protection and Research
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• 제34권2호
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• pp.87-94
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• 2009

삼중수소는 중수로형 원전에서 방사선작업종사자의 내부피폭을 일으키는 주요 방사성핵종 중의 하나이다. 이 핵종은 계통에서 HTO 형태로 비교적 쉽게 누설되며, 호흡과정을 통해 작업종사자의 신체내부로 유입된다. 이러한 삼중수소는 신체 내에서 약 2시간 후에 평형에 도달하며, 약 10일의 유효반감기를 가지고 신체로부터 제거된다. 신체내의 삼중수소는 체액을 따라 유동하기 때문에 전신이 피폭을 받게 된다. 원전의 운영경험에 의하면 원전종사자의 전체 피폭방사선량의 약 20$\sim$40% 정도가 삼중수소에 의한 내부피폭으로 발생하고 있다. 따라서, 원전의 방사선안전관리 측면에서 볼 때 중요하게 관리되는 방사성핵종이다. 본 논문에서는 중수로 원전에서 삼중수소의 흡입에 따른 뇨시료 중의 삼중수소 방사능 측정 자료를 이용하여 삼중수소의 인체 대사모델을 수립하고, 이를 근거로 피폭방사선량 평가의 중요 인자인 유효반감기를 분석하였다. 이 결과에 따르면 국내 원전 종사자의 유효반감기는 국제방사선 방호위원회에서 제시한 10일보다 짧은 것으로 나타났다.

• Journal of Radiation Protection and Research
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• 제32권3호
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• pp.111-115
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• 2007

원자력 발전소의 중수누출에 따른 삼중수소 농도증가에 의한 방사선 내부피폭과 이에 대한건강영향평가를 실시하였다. 전체 22명 가운데 13명에 대하여 검사를 실시하였으며, 이들의 내부피폭량은 $0{\sim}4.44\;mSv$ 였다. 일반혈액검사 중 백혈구수치의 변화를 이용하여 평가한 결과에서 결정적 영향에 대한 특이사항은 나타나지 않았으며, 생물학적 선량평가 방법을 이용한 체내피폭량은 $0{\sim}37\;mGy$로 확인되었다. 결론적으로 방사선 피폭은 허용한도를 초과하지 않았으며, 결정적 영향인 임상적 증상이 보이지 않았다. 이와 같이 의학적 징후와 선량평가 추정치와의 일치성은 사고시 특히 물리적 생물학적 선량평가가 유용함을 보여 준다.

• 대한방사선기술학회지:방사선기술과학
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• 제41권5호
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• pp.437-444
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• 2018

Whole-Body counters have been used to evaluate the internal contamination of gamma emitting radionuclides. Among the whole-body counters used in domestic nuclear facilities, Fastscan made by CANBERRA contains 2 NaI(Tl) detectors and is generally used to monitor the primary internal exposure. It has the advantage of achieving MDA even with short time measurements. Accuscan is a bed type, and has good energy resolution because it is composed of HPGe detector. Since the Accuscan with better energy resolution than Fastscan has better able to identify radionuclides, it is used to monitor secondary internal exposure. Some nuclear facilities have only Fastscan. We analyzed statistically whether Fastscan is enough to ensure accuracy and precision comparing with Accuscan. To do this, we prepared a CRM created by the Korea Research Institute of Standards and Science. We also obtained the data of 6 Fastscans and 5 Accuscans in domestic nuclear facilities. As a result of the study, although Fastscan compared with Accuscan is not as accurate as the Accuscan, the precision is statistically same. However, accuracy of Fastscan is in compliance with international standards except low energy range. In terms of accuracy and precision except radionuclides emitting low energy, it is possible to measure radioactivity inside workers even in nuclear facilities where only Fastscan is used.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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• pp.317-320
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• 2005

방사선방호 신개념(ICRP-60)이 국내에서 법제화되어 2003년부터 시행됨에 따라 원자력발전소에 대한 보다 엄격해진 방사선방호 기준이 적용되고 있다 특히, 중수로 원자력발전소의 경우 $^{14}C$와 삼중수소로 인한 방사선작업종사자에 대한 방사선 위해가 경수로 원자력발전소보다 상대적으로 의기 때문에 작업종사자의 내부피폭 선량을 정확하게 측정하고 평가하여 내부피폭을 예방하는 노력이 필요하다. 본 보고서에는 중수로 원자력발전소에서 발생된 $^{14}C$의 체내 흡입으로 인한 방사선 작업종사자의 내부피폭 선량평가 방법을 정립하기 위해 예비적으로 $^{14}C$로 인한 인체대사모델을 분석하였고 $^{14}C$에 대한 내부피폭 선량평가 방법을 기술하였다.

• 방사선산업학회지
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• 제17권2호
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• pp.161-172
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• 2023

Coal-fired power plants handle large quantities of coal, one of the most prominent NORM, and the coal ash produced after the coal is burned can be tens of times more radioactive than the coal. Workers in these industries may be exposed to internal exposure by inhalation of particles while handling NORM. This study evaluated the size, concentration, particle shape and density, and radioactivity concentrations of airborne suspended particles in the main processes of a coal-fired power plant. Finally, the internal radiation dose to workers from particle inhalation was evaluated. For this purpose, airborne particles were collected by size using a multi-stage particle collector to determine the size, shape, and concentration of particles. Samples of coal and coal ash were collected to measure the density and radioactivity of particles. The dose conversion factor and annual radionuclide inhalation amount were derived based on the characteristics of the particles. Finally, the internal radiation dose due to particle inhalation was evaluated. Overall, the internal radiation dose to workers in the main processes of coalfired power plants A and B ranged from 1.47×10^-5~1.12×10^-3 mSv y^-1. Due to the effect of dust generated during loading operations, the internal radiation dose of fly ash loading processes in both coal-fired power plants A and B was higher than that of other processes. In the case of workers in the coal storage yard at power plants A and B, the characteristic values such as particle size, airborne concentration, and working time were the same, but due to the difference in radioactivity concentration and density depending on the origin of the coal, the internal radiation dose by origin was different, and the highest was found when inhaling coal imported from Australia among the five origins. In addition, the main nuclide contributing the most to the internal radiation dose from the main processes in the coal-fired power plants was thorium due to differences in dose conversion factors. However, considering the external radiation dose of workers in coal-fired power plants presented in overseas research cases, the annual effective dose of workers in the main processes of power plants A and B does not exceed 1mSv y^-1, which is the dose limit for the general public notified by the Nuclear Safety Act. The results of this study can be utilized to identify the internal exposure levels of workers in domestic coal-fired power plants and will contribute to the establishment of a data base for a differential safety management system for NORM-handling industries in the future.

• Journal of Radiation Protection and Research
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• 제49권1호
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• pp.1-18
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• 2024

Exponential growth has been observed in nuclear medicine procedures worldwide in the past decades. The considerable increase is attributed to the advance of positron emission tomography and single photon emission computed tomography, as well as the introduction of new radiopharmaceuticals. Although nuclear medicine procedures provide undisputable diagnostic and therapeutic benefits to patients, the substantial increase in radiation exposure to nuclear medicine patients raises concerns about potential adverse health effects and calls for the urgent need to monitor exposure levels. In the current article, model-based internal dosimetry methods were reviewed, focusing on Medical Internal Radiation Dose (MIRD) formalism, biokinetic data, human anatomy models (stylized, voxel, and hybrid computational human phantoms), and energy spectrum data of radionuclides. Key results from many articles on nuclear medicine dosimetry and comparisons of dosimetry quantities based on different types of human anatomy models were summarized. Key characteristics of seven model-based dose calculation tools were tabulated and discussed, including dose quantities, computational human phantoms used for dose calculations, decay data for radionuclides, biokinetic data, and user interface. Lastly, future research needs in nuclear medicine dosimetry were discussed. Model-based internal dosimetry methods were reviewed focusing on MIRD formalism, biokinetic data, human anatomy models, and energy spectrum data of radionuclides. Future research should focus on updating biokinetic data, revising energy transfer quantities for alimentary and gastrointestinal tracts, accounting for body size in nuclear medicine dosimetry, and recalculating dose coefficients based on the latest biokinetic and energy transfer data.