• Nuclear Engineering and Technology
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• 제53권1호
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• pp.351-356
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• 2021

Korean nuclear power plants (NPPs) have various radiation protection programs to attain radiation exposure as low as reasonably achievable (ALARA). In terms of ALARA, this paper provides a comprehensive overview of administrative dose control for occupationally-exposed workers in Korean NPPs. In addition to dose limits, administrative dose constraints are implemented to resolve an inequity of radiation exposure in which some individuals in NPPs receive relatively higher doses than others. Occupational dose constraints in Korean NPPs are presented in this paper with the background of how those values were determined. For pressurized water reactors, 80% and 90% of the annual average limit for an effective dose, 20 mSv/y, are set as the primary and secondary dose constraints, respectively. Pressurized heavy water reactors (PHWRs) have also established the primary and secondary dose constraints corresponding to 70% and 80% of the effective dose limit, and additional constraints for tritium concentration are provided to control internal exposure in PHWRs. Follow-up measures for exceeding these administrative dose constraints are also introduced compared to exceeding the dose limits. Finally, analysis results of dose distributions show how the implementation of administrative dose constraints impacted the occupational dose distributions in Korean NPPs during the years 2009-2018.

• 핵의학기술
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• 제15권2호
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• pp.3-12
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• 2011

본 연구는 방사성동위원소의 의학적 이용도가 증가함에 따라 의료기관 핵의학과 방사선관계종사자의 직무별 방사선 이용에 대한 개인 방사선피폭선량의 실태를 파악하여, 방사선 위험에 대해 경각심을 고취시키고, 방사선 관계종사자들에게 안전관리와 합리적인 피폭선량 관리에 도움을 주고자 분석하였다. 2010년 1월 1일부터 2010년 12월 31일까지 의료기관에서 근무하는 방사선종사자로 분류되어 개인 방사선피폭선량 측정을 정기적, 연속적으로 1년간 조사 관리된 540명의 종사자를 대상으로 부서별, 선량영역구간별, 근무기간별, 직무별 관련업무를 파악하여 심부선량에 대하여 연간평균피폭선량을 각각 분석하였다. 분석법으로는 빈도분석과 ANOVA를 시행하였다. 의료기관 방사선종사자의 부서별 연간피폭선량은 핵의학과 4.57 mSv로 가장 높았으며, 심장혈관중재술실 2.09 mSv, 마취통증의학과 1.42 mSv, 영상의학과 1.10 mSv, 구강악안면 방사선과 0.59 mSv, 방사선종양학과 0.50 mSv 순으로 높게 나타났다. 선량영역별 분포는 핵의학과, 심장혈관중재술실에서 5.01~19.05 mSv의 높은 선량영역분포를 보였으며, 부서별 방사선사의 연간피폭선량은 핵의학과 7.14 mSv로 가장 높은 피폭선량을 보이고 있으며, 심장혈관중재술실 1.46 mSv로 높았고, 영상의학과 0.97 mSv, 구강악안면방사선과 0.66 mSv, 방사선종양학과 0.54 mSv 순으로 나타났다. 세부업무에 따른 직무별 연간평균피폭선량은 싸이크로트론 관련 합성 업무 17.47 mSv로 가장 높은 피폭선량을 보였으며, Gamma camera 영상실 7.24 mSv, PET/CT 영상실 업무가 7.60 mSv로 높게 나타났고, 인터벤션 2.04 mSv, 심혈관중재술실 1.46 mSv, 일반촬영 1.21 mSv, Primart 치료실 0.90 mSv, 구강악안면방사선과 일반촬영 0.66 mSv 순으로 나타났다. 근무기간별, 선량영역별에 따른 연간평균피폭선량은 구강악안면방사선과에서는 10~14년 종사자가 1.01~3.00 mSv로 높은 평균선량을 보였고, 방사선종양학과는 모든 근무기간에 따라 0.00~1.00 mSv 의 낮은 선량영역구간에서 분포를 보였으며, 심혈관중재술실은 10~14년, 15~19년 근무에 따라 각각 1.01~3.00 mSv 선량영역구간에서 분포하였으며, 영상의학과에서는 1~4년, 5~9년 종사자가 각각 1.01~8.00 mSv의 가장 높은 선량영역구간에서 분포를 보였고, 핵의학과에서는 1~4년, 5~9년 종사자가 각각 3.01~19.05 mSv 의 가장 높은 선량영역구간에서 분포를 보였으며, 10~14년, 15~19년 종사자에서도 각각 3.01~15.00 mSv의 높은 선량영역구간에서 분포를 보였다. 이와 같은 결과로 볼 때 의료기관에서 근무하는 방사선관계종사자의 대부분이 현재의 방사선 안전관리가 실효성 있게 이루어지고 있었으며, 직무특성에 따라 많은 차이가 있는 것을 알게 되었다. 그러나 방사선 피폭을 최소화시키는 노력이 필요하며, 이를 위해서 체계적 교육과 합리적인 피폭량 관리를 위한 체계가 필요하다고 사료된다.

• Journal of Radiation Protection and Research
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• 제40권3호
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• pp.162-167
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• 2015

후쿠시마 원전 사고로 인한 우리나라 장기 전력수급정책에 대한 대중의 저항 및 불안감이 존재하고 있다. 고리 원전 1호기에 대한 정부의 영구정지 결정과 설계수명이 끝난 월성 원전 1호기의 계속운전 시행 반대, 고리 원전 인근 주민의 갑상선암 논란 등 원전 운영으로 인한 국내외 여건이 위기를 맞이하고 있다. 이러한 상황에서 원전운영능력과 안전은 여러 가지 지표들이 있지만, 원전의 방사선안전관리 능력, 특히 방사선피폭량을 중심으로 상세 분석과 논의가 필요하다. 분석대상과 방법으로는 최근 5년간 원전의 피폭 방사선량을 분석하고, 유관한 방사선 작업종사자군과 방사선 피폭량 추이를 비교 평가하였고, 세계 주요 원전 국의 개인당 연간 평균방사선량도 비교 분석하였다. 분석결과 방사선차폐와 방호조치등 총체적인 방사선량 저감화 계획과 연구를 통해 방사선피폭량을 저감하고 있음을 확인하였다. 연간선량한도한도인 50 mSv, 5년간 100 mSv를 초과한 방사선작업 종사자는 없었으며, 이는 방사선구역 출입시 자동화에 따른 출입제한과 관리선량 제한치를 연간선량한도의 60%미만으로 설정하는 등 다양한 방사선안전관리 체계를 확보하고 있음이 확인되었다. 원자로형별 운영형태에 따른 방사선피폭 유형은, 중수로 원전의 총 피폭대비 정상 운전시 방사선피폭비율이 경수로 원전보다 6.2 % 높게 나타났다. 이는 중수로 원전이 정상운전시 방사선피폭 작업이 많음을 확인하였다. 또한 세계원자력발전사업자협의회 성능평가지표(World Association of Nuclear Operators performance indicators, WANO PI)에 의하면, 2013년도 주요 원전보유국의 연간 호기당 집단선량은 우리나라가 527 man-mSv로 가장 우수한 실적을 보였으며, 세계평균치인 725 man-mSv의 73% 수준을 보이는 것으로 나타났다. 개인당 연간 방사선피폭량은 종사자의 약 80%가 일반인의 선량한도인 1 mSv 미만이며, 개인당 평균선량 역시 0.82 mSv로 매우 낮은 수준을 보였다. 유관 기관의 방사선작업 종사자와 비교해보면, 2013년 기준으로 방사선안전재단에 등록된 관련 업종 방사선작업 종사자의 개인당 평균선량은 1.07 mSv에 비해 77% 수준이며, 비파괴 검사기관 종사자의 개인 평균선량 3.87 mSv의 21% 수준을 보였다. 결론적으로 원전의 피폭 방사선량은 이상적으로 저감하는 추이를 보이고 있으나, 더 이상 낮추는 것은 한계가 있을 것으로 판단된다. 그러나 원전 주변 주민이 심리적인 불안감, 전원개발계획에서 원전의 비중을 감안할 때, 최적의 원전 상황을 평가하는 지표인 방사선안전관리 능력은 각종 통계를 기반으로 하는 정보 제시 및 총체적인 방사선량 저감화 추진이 필요할 것으로 판단된다.

• 대한방사선기술학회지:방사선기술과학
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• 제43권2호
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• pp.123-128
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• 2020

Radiation Following the 2011 Fukushima nuclear accident in Japan, public interest and anxiety about radiation safety increased, and vague anxiety about commonly exposed living radiation was generated. The Atomic Energy Safety Commission has been conducting a survey of processed products that advertise "negative ions" and "far-infrared" emissions under the Living Radiation Safety Management Act. In this study, in-depth analysis was performed from a statistical point of view using the measurement data presented in the Nuclear Safety Committee's actual survey analysis report as secondary data. As a result, there was a statistically significant difference (p<0.005) between latex and civil affairs products. There were also statistically significant differences (p<0.05) in the results of testing whether there were significant differences in the annual exposure dose between groups after categorizing 71 civil products, including radon beds, into bed, bedding, and living and other categories. The correlation analysis results also confirm that, as is commonly known, the annual doses received from processed products are associated with radon derived from U-238 and Th-232.

• 핵의학기술
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• 제16권1호
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• pp.50-56
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• 2012

일시 출입자로 분류된 핵의학과 출입 환경미화원은 주기적으로 타과와 업무순환을 하고, 또한 작업 시간과 환경 등의 변화가 많기 때문에 관리하기에 어려운 점이 있으며 따라서 이들의 분류를 명확히 할 필요가 있다. 이에 본 논문에서는 핵의학과에서 근무하는 환경미화원의 피폭 상황을 분석하여 일시 출입자로 분류된 조건의 타당성에 대하여 검토해 보고 작업 환경의 변화 및 근무 시간의 조절이 필요한가를 알아보았다. 우선 먼저 PET실과 혈액 검사실에서 근무하는 환경미화원과 감마 카메라실에서 근무하는 환경 미화원 2명을 대상으로 한 달간 근무 시간 중에 OSL을 각각 착용시켜 개인 피폭 선량을 측정하였다. 둘째로 survey meter를 이용하여 두 명의 환경미화원의 작업 환경, 근무 형태에 따라 시간대 별로 핵의학과 내 14개 구역을 선정, 총 10회 공간 선량률을 측정한 결과 이들의 피폭 선량은 연간 1mSv를 초과하지 않았으며, survey meter를 이용하여 조사한 결과 또한 연간 1 mSv를 초과하지 않을 것으로 추정되지만 그 수치가 1 mSv에 근접하였다. 따라서 일시 출입자로써의 분류를 좀 더 명확히 하기 위해서는 PET 안정실과 같은 피폭이 상대적으로 많은 구역에서의 노출 확률을 줄이기 위하여 이들에게 방사선 관리 구역내 교육을 실시하고, 또한 근무시간 및 근무 형태를 적절히 변경한다면 이들의 피폭 선량은 확연히 줄어들 것으로 사료된다.

• 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.

• 보존과학연구
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• 통권26호
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• pp.189-202
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• 2005

This study carried out to understand thermoluminescence dating of ancient tiles at Jinju Janghungri Kilin site. Also radiocarbon dating by the benzene synthesis method and Liquid scintillation counting method were performed for comparison for the agedetermination of charcoal sample at the obtained same site.1st and 2nd glow curve were obtained according to the typical method thermoluminescence. Plateau tests of revealed the proper temperature range to be $300~440^{\circ}C$ Palaeodose average values were formed to the 2.44Gy.Annual dose of ancient tiles was calculated from soil samples and ancient tiles it self by measuring alpha radiation dose, potassium concentrations and water contents respectively. Annual dose average values were calculated to be 7.012mGy/yr.The radiocarbon age(BP year) was converted to calibrated age(AD/BC year) using high precision curve. Radiocarbon ages were calculated to be AD 15~17 .Comparison of samples with their radiocarbon and thermoluminescence ages for revealed the in range the AD 15~17. This result means that the measured absolute ages are in good agreement with each other within the margin of error.

• 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.

• 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 Korean Neurosurgical Society
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• 제63권4호
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• pp.415-426
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• 2020

Arteriovenous malformations (AVMs) are congenital anomalies of the cerebrovascular system. AVM harbors 2.2% annual hemorrhage risk in unruptured cases and 4.5% annual hemorrhage risk of previously ruptured cases. Stereotactic radiosurgery (SRS) have been shown excellent treatment outcomes for patients with small- to moderated sized AVM which can be achieved in 80-90% complete obliteration rate with a 2-3 years latency period. The most important factors are associated with obliteration after SRS is the radiation dose to the AVM. In our institutional clinical practice, now 22 Gy (50% isodose line) dose of radiation has been used for treatment of cerebral AVM in single-session radiosurgery. However, dose-volume relationship can be unfavorable for large AVMs when treated in a single-session radiosurgery, resulting high complication rates for effective dose. Thus, various strategies should be considered to treat large AVM. The role of pre-SRS embolization is permanent volume reduction of the nidus and treat high-risk lesion such as AVM-related aneurysm and high-flow arteriovenous shunt. Various staging technique of radiosurgery including volume-staged radiosurgery, hypofractionated radiotherapy and dose-staged radiosurgery are possible option for large AVM. The incidence of post-radiosurgery complication is varied, the incidence rate of radiological post-radiosurgical complication has been reported 30-40% and symptomatic complication rate was reported from 8.1% to 11.8%. In the future, novel therapy which incorporate endovascular treatment using liquid embolic material and new radiosurgical technique such as gene or cytokine-targeted radio-sensitization should be needed.