• 한국방사선학회논문지
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• 제6권1호
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• pp.27-37
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• 2012

2002년 1월 1일부터 2011년 6월 30일까지 지방의 C 대학병원 방사선 관계 종사자 의사, 간호사, 방사선사 및 기타 323명에 대한 개인피폭 선량 측정결과 4419건을 비교 분석하였다. 연도별로는 2003년도 수치가 가장 높았고, 2007년도 수치가 낮게 나타났다. 성별로는 남성이 여성에 비해 높고 연령대는 30대가 높았으며 직종별로는 의사, 간호사, 방사선사 순으로 나타났다. 근무부서별 평균피폭선량은 심혈관 센터, 인터벤션실, 영상의학과(의사), 투시촬영실 순으로 높은 수치를 나타냈다. 이상의 결과로 볼 때 ICRP에서 권고하는 허용선량 기준치(20mSv/년)를 초과하지 않는 범위의 피폭을 받고 있는 것으로 나타났다. 그러나 평균치와 달리 선량의 개인편차가 심하기 때문에 피폭의 최소화를 위해서 방사선 관련 종사자들이 개인별 피폭관리에 최선을 다해야 할 것이다.

• 방사선산업학회지
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• 제11권3호
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• pp.123-130
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• 2017

Concerns about high radiation exposure to the hands of radiation workers who may contact with radioactive contamination on surfaces in a nuclear power plant (NPP) had been raised, and the Korean regulatory body required the extremity dose estimation during contact tasks with radioactive materials. Korean NPPs conducted field tests to identify the incident radiation to the hands of radiation workers who may contact with radioactive contamination during maintenance periods. The results showed that the radiation fields for contact tasks are dominated by high energy photons. It was also found that the radiation doses to the hands of radiation workers in Korean NPPs were much less than the annual dose limits for extremities. This approach can be applicable to measure and estimate the extremity dose to the hands of medical workers who handle the radioactive materials in a hospital.

• 방사성폐기물학회지
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• 제21권2호
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• pp.183-191
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• 2023

The potential impact of hypothetical accidents that occur during the immediate and deferred dismantling of the Kori Unit 1 steam generator has been comprehensively evaluated. The evaluation includes determining the inventory of radionuclides in the Steam Generator based on surface contamination measurements, assuming a rate of release for each accident scenario, and applying external and internal exposure dose coefficients to assess the effects of radionuclides on human health. The evaluation also includes calculating the atmospheric dispersion factor using the PAVAN code and analyzing three years of meteorological data from Kori NPP to determine the degree of diffusion of radionuclides in the atmosphere. Overall, the effective dose for residents living in the Exclusion Area Boundary (EAB) of Kori NPP is predicted, an it is found that the maximum level of the dose is 0.034% compared to the annual dose limit of 1 mSv for the general public. This implies that the potential impact of hypothetical accidents on human health discussed above is within acceptable limits.

• Journal of Radiation Protection and Research
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• 제32권3호
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• pp.97-104
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• 2007

전주시에 소재한 아파트의 큰 방과 작은 방을 대상으로 실내 체적과 측정되는 라돈 농도와의 상관 관계를 분석하였다. 또한 실내의 라돈 농도를 측정하여 실내의 시간별 라돈 농도의 변화를 파악하고 이를 토대로 실내 라돈의 년간 피폭선량을 계산하였다. 본 연구를 위하여 각각 8개의 아파트 큰 방과 작은 방을 대상으로 라돈 농도를 측정하였으며, 큰 방의 평균 체적은 $31.59\;m^3$ 그리고 작은 방의 평균 체적은 $16.82\;m^3$이었다. 큰 방의 평균 라돈 농도는 $71.73\;Bq/m^3$, 작은 방의 평균 라돈 농도는 $108.51\;Bq/m^3$로 측정되어 실내 체적과 실내 라돈 농도는 반비례 관계로 나타났다. 밀폐된 실내 라돈 농도의 주 발생원이 건축자재임을 감안하여 건물 벽의 표면적을 체적으로 나누어 계측해 본 결과 표면적/체적의 비가 클수록 측정되는 실내 라돈 농도가 크게 나타났다. 실내 라돈 농도의 하루 중 시간에 따른 변화를 조사한 결과 오전 $8{\sim}10$시에 일 최고 농도($114.5\;Bq/m^3$)를 보였고, 오후 $2{\sim}4$시에 일 최저농도($67.7\;Bq/m^3$)를 나타냈으며, 하루 중 라돈 농도의 변화는 약 $46.8\;Bq/m^3$이었다. 8개 지점의 실내 라돈의 연간 피폭선량을 계산해 본 결과 0.3에서 2.16 mSv/yr사이로 나타나, 일부 아파트의 피폭선량이 국제방사선영향과학위원회(UNSCEAR)가 제시한 수치인 1.3 mSv/yr를 초과했다.

• 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.

• 방사성폐기물학회지
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• 제17권1호
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• pp.107-120
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• 2019

다수호기 부지에 위치한 원전의 해체는 인근에 위치한 운영중인 원전으로 인해 작업자에게 추가적인 방사선 피폭 위험을 야기할 수 있다. 따라서 인근의 운영중인 다수호기 원전에 의한 해체 작업자에 대한 피폭 선량 평가가 필요하다. ENDOS프로그램은 한국원자력연구원(KAERI)에서 개발된 선량평가 전산코드로, 하위 프로그램으로 대기 확산 평가 프로그램인 ENDOS-ATM과 기체 방사성 배출물에 의한 피폭 선량 계산을 수행하는 ENDOS-G가 있다. 이 프로그램들을 이용하여 고리 1호기 해체작업자에 대한 다수호기 원전 운영에 의한 피폭 선량을 계산한 결과, $2.31{\times}10^{-3}mSv{\cdot}y^{-1}$로 일반인에 대한 피폭선량 기준치인 $1mSv{\cdot}y^{-1}$에 비교해 보았을때 큰 영향이 없을 것이라는 판단에 도달할 수 있었다. 앞으로 예상되는 국내 해체 원전의 경우 모두 다수호기 부지에 위치하여 이 연구 방법과 결과가 활용될 수 있을 것이라고 기대한다.

• 한국안전학회지
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• 제24권6호
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• pp.157-162
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• 2009

Radioactive medicines are used a lot owing to the increase of a PET-CT examination using glucose metabolism useful for the early diagnosis of diseases. Therefore, the spatial dose that is generated from patients and their surroundings causes the patients' guardians and health professional to be exposed to radiation. However, they get unnecessarily exposed to radiation because medical institutions lack in space for isolation and recognition of the examination. This research intended to examine the spatial dose rates by measuring the dose emitted from the patient for 48 hours to whom F-18 FDG was administered. The spatial dose rates that were measured 100cm away from the patient's body after F-18 FDG was injected were $65.88{\mu}$Sv/hr at 60-minute point, $45.13{\mu}$Sv/hr at 90-minute point, $9.88{\mu}$Sv/hr at 6-hour point, and $1.24{\mu}$Sv/hr at 12-hour point. When the dose that the guardian and health professional got was converted into the annual(240-day working) accumulative dose, it was examined that the guardian received 81.56 mSv/yr and health professional received 49.36mSv/yr. In addition, the result has revealed that the dose that the patient received from one time of PET-CT examination was 3.75mSv/yr, which is 1.5 times more when compared with the annual natural radiation exposure dose.

• The Korean Journal of Pain
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• 제35권2호
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• pp.129-139
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• 2022

C-arm fluoroscopy is a useful tool for interventional pain management. However, with the increasing use of C-arm fluoroscopy, the risk of accumulated radiation exposure is a significant concern for pain physicians. Therefore, efforts are needed to reduce radiation exposure. There are three types of radiation exposure sources: (1) the primary X-ray beam, (2) scattered radiation, and (3) leakage from the X-ray tube. The major radiation exposure risk for most medical staff members is scattered radiation, the amount of which is affected by many factors. Pain physicians can reduce their radiation exposure by use of several effective methods, which utilize the following main principles: reducing the exposure time, increasing the distance from the radiation source, and radiation shielding. Some methods reduce not only the pain physician's but also the patient's radiation exposure. Taking images with collimation and minimal use of magnification are ways to reduce the intensity of the primary X-ray beam and the amount of scattered radiation. It is also important to carefully select the C-arm fluoroscopy mode, such as pulsed mode or low-dose mode, for ensuring the physician's and patient's radiation safety. Pain physicians should practice these principles and also be aware of the annual permissible radiation dose as well as checking their radiation exposure. This article aimed to review the literature on radiation safety in relation to C-arm fluoroscopy and provide recommendations to pain physicians during C-arm fluoroscopy-guided interventional pain management.

• 방사선산업학회지
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• 제18권2호
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• pp.117-126
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• 2024

This study aims to identify high exposure tasks among the tasks performed in domestic nuclear power plants as a basis for developing training programs to improve the efficiency of workers' work. To this end, we first analyzed the exposure status of radiation work in domestic nuclear power plants. Radiation tasks in nuclear power plants were categorized, collective doses were investigated, and the collective doses were calculated based on the collective doses, and representative high exposure tasks were identified. We found that the collective and individual doses in domestic nuclear power plants are continuously decreasing, but there is an imbalance of exposure among workers. In terms of work classification, nuclear power plants are managed in 236 work codes based on light water reactors and 181 work codes based on heavy water reactors, depending on the work equipment and location. Among the total work codes, 23 codes have an annual average dose exceeding 10 μSv, and based on this, 10 representative high exposure tasks were derived. The representative high exposure tasks were selected as S/G nozzle dam work, S/G debris removal work, nuclear instrumentation system, S/G eddy current detection work, and insulation work. The results of this study are expected to serve as an important basis for reducing the exposure of workers in nuclear power plants and improving work efficiency.

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.2085-2091
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• 2020

The license for Kori-1, the first commercial reactor in Busan, Korea, was terminated in June 2017; therefore, preparations are being made for its decommissioning. Because the radioactivity of Bio-shield varies greatly throughout the structure, the doses received by the workers depend on the location, order, and duration of dismantling operations. Thus, a model for evaluating the worker external dose during the dismantling of the Kori-1 bio-shield was developed, and work scenarios for dose assessment were designed. The Dose evaluation code VISIPLAN was used for dose assessment. The dose rate around the bio-shield was evaluated and the level of exposure to the operator was evaluated according to the work scenario. The maximum annual external dose was calculated as 746.86 mSv for a diamond wire saw operator under dry cutting conditions, indicating that appropriate protective measures, such as changing dismantling sequence, remote monitoring, shield installation, and adjustment of work team are necessary for the safe dismantling of the bio-shield. Through these protective measures, it was found that the worker's dose could be below the dose limit.