• 디지털융복합연구
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• 제13권10호
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• pp.377-383
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• 2015

본 연구는 방사선을 이용한 검사 시 방사선 방어용 앞치마(apron)의 성능이 좋지 못할 경우 방사선 작업종사자의 피폭이 상대적으로 높아질 수밖에 없음에 따라 영상평가 프로그램인 Image J의 최대 신호 대 잡음비 값을 측정하여 융복합 방어 성능평가와, 우수한 성능의 apron을 구비 할 수 있는 기초자료를 도출하고, 선량계 없이도 성능 평가 방법의 접근을 용이하게 하여 주기적이고 철저한 apron관리의 용이성을 확보하고자 하였다. 각각 32벌의 apron 9군데의 최대 신호 대 잡음비 값을 비교한 결과 상태가 양호한 apron의 경우 27 dB이상으로 나타났고 상태가 불량한 apron의 경우 24 dB미만으로 측정되어 각각의 성능이 뚜렷하게 구별 되는 것이 확인되었다. 통계분석결과 정규성 분포를 보여 t-test를 실시한 결과 p<0.001로 두 결과 값은 통계적으로 유의하였다. 이에 따라 방사선 작업종사자의 방사선피폭을 최대한 줄이기 위해 선량계 없이 최대 신호 대 잡음비 값 측정만으로 apron의 성능 평가가 용이하여 방사선 작업종사자 및 환자의 불필요한 피폭 관리가 용이하게 되었다.

• 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.

• 디지털융복합연구
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• 제10권2호
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• pp.249-254
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• 2012

인체조직등가 팬텀과 유리선량계를 활용하여 최근 임상에서 사용되고 있는 이용 128채널 MDCT과 4채널 MDCT의 복부 촬영시 피폭선량과 획득영상의 화질을 평가하였다. 복부 CT 검사 시 흡수선량은 4-MDCT에서 $35.8{\pm}0.46mGy$, 128-MDCT에서 $19.03{\pm}0.25mGy$로 나타나 진단에 의미있는 영상을 획득하는데 필요한 방사선량은 128-MDCT가 적게 요구되는 것으로 나타났다(P<0.05). MDCT를 이용한 복부 검사에서 획득한 영상을 Likert 5점 척도로 분석한 결과 4-MDCT 경우가 3.52점의 결과를 보였으며, 128-MDCT경우 4.01점의 결과를 나타내어 128-MDCT의 영상의 질이 높게 평가되었으며 통계적으로도 유의한 차이가 있었다(p<0.05). 이상의 결과에서 128-MDCT는 방사선피폭량을 줄일 수 있고 높은 영상의 질을 얻을 수 있어 향후 많은 이용이 될 것으로 사료된다.

• 방사선산업학회지
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• 제18권2호
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• pp.147-153
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• 2024

Radioactive liquid waste generated during operation and overhaul is collected and reused through the radioactive liquid waste treatment system and continuous monitoring system in the nuclear power plant or discharged to the outside if it satisfies the limit within the control and monitoring. However, there are concerns about boric acid management, which controls the power output of nuclear power plants in radioactive liquid waste. Due to the behavior of boric acid, it is difficult to remove it in the existing liquid radwaste system, and the concentration of boric acid water discharged tends to be higher than the natural state of 5 ppm, so additional facilities should be considered. Therefore, this study aims to evaluate the radiological effects of radioactive waste treatment facilities that are under development and use them as a basis for managing worker exposure and evaluating the safety of facilities in the future.

• 한국의학물리학회지:의학물리
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• 제20권4호
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• pp.253-259
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• 2009

방사선관계종사자에 대한 개인피폭선량 측정의 정확성 및 신뢰성을 확보함으로써 방사선관계종사자의 건강을 보호하고 국민보건 수준향상에 기여하기 위한 개인피폭선량 측정기관의 선량측정 품질관리 기준을 국제기준에 적합하도록 개발할 필요성이 제기되고 있다. 국내 의료기관에서의 개인선량 관련법은 ANSI N13.11-1993 규정을 참조하고 있으나 미국을 비롯한 해외 여러 나라에서는 시험 범주를 줄이고 기준을 강화한 ANSI N13.11-2001을 이미 반영하여 개인피폭선량을 측정하고 있다. 제안하는 방법은 ANSI N13.11-2001을 참고하여 기준을 단순화하였고 유리선량계와 광자극선량계 같은 현재 법률에서 인정하지 않는 첨단기술을 이용하는 것을 막거나 방해할 수 있는 조치를 취하지 않으려고 하였다. 본 논문에서 제안하는 측정기관 품질관리기준은 개인피폭선량 성능시험기준은 관련법규개정에 참고할 수 있고, 측정기관 지도 감독에 활용할 수 있다.

• 대한안전경영과학회지
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• 제17권4호
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• pp.213-221
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• 2015

The aim of this study was to set up the optimal exposure condition according to detector type considering image quality (IQ) with radiation dose in chest digital radiography. We used three detector type such as flat-panel detector (FP) and computed radiography (CR), and charge-coupled device (CCD). Entrance surface dose (ESD) was measured at each exposure condition combined tube voltage with tube current using dosimeter, after attaching on human phantom, it was repeated 3 times. Phantom images were evaluated independently by three chest radiologists after blinding image informations. Standard exposure condition using each institution was 117 kVp-AEC at FP and 117 kVp-8 mAs at CR, and 117 kVp-8 mAs at CCD. Statistical analysis was performed by One way ANOVA (Dunnett T3 test) using SPSS ver. 19.0. In FP, IQ scores were not significant difference between 102 kVp-4 mAs and 117 kVp-AEC (28.4 vs. 31.1, p=1.000), even though ESD was decreased up to 50% ($62.3{\mu}Gy$ vs. $125.1{\mu}Gy$). In CR, ESD was greatly decreased from 117 kVp-8 mAs to 90 kVp-8 mAs without significant difference of IQ score (p=1.000, 24.6 vs. 19.5). In CCD, IQ score of 117 kVp-8 mAs was similar with 109 kVp-8 mAs (29.6 vs. 29.0), with decreasing from $320.8{\mu}Gy$ to $284.7{\mu}Gy$ (about 11%). We conclude that optimal x-ray exposure condition for chest digital radiography is 102 kVp-4 mAs in FP and 90 kVp-8 mAs in CR, and 109 kVp-8 mAs in CCD.

• 디지털융복합연구
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• 제11권6호
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• pp.269-273
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• 2013

치과 진료시 파노라마 장치를 이용한 검사에서 유리선량계를 사용하여 피검자의 피폭선량을 측정하였다. 특히 방사선에 민감한 수정체의 피폭선량을 줄이기 위하여 자체 제작한 Pb밴딩의 크기에 따라 수정체 피폭선량을 측정한 결과 Pb밴딩의 크기에 따라서 수정체의 피폭선량이 다르다는 것을 확인할 수 있었다. Pb밴딩의 크기가 $3{\times}20{\times}0.2cm$에서는 정상치보다 피폭선량이 증가하는 경향을 보였으며 $5{\times}20{\times}0.2cm$ 이상의 크기에서는 피폭선량이 감소하는 결과를 보였다. 또한 획득되어진 영상 $7{\times}20{\times}0.2cm$ 크기에서 진단에 부적합한 영상으로 판정되었다. 그러므로 피폭선량을 최소화하고 효과적인 파노라마 검사를 수행하기 위해서는 Pb밴딩 $5{\times}20{\times}0.2cm$이상 $6{\times}20{\times}0.2cm$이하 크기를 사용하여 검사에 활용하면 피폭선량이 감소될 것으로 기대한다.

• 방사성폐기물학회지
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• 제21권3호
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• pp.371-381
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• 2023

Evaluating the effectiveness of the radiation protection measures deployed at the Centralized Radioactive Waste Management Facility in Ghana is pivotal to guaranteeing the safety of personnel, public and the environment, thus the need for this study. Radiagem^TM 2000 was used in measuring the dose rate of the facility whilst the personal radiation exposure of the personnel from 2011 to 2022 was measured from the thermoluminescent dosimeter badges using Harshaw 6600 Plus Automated TLD Reader. The decay store containing scrap metals from dismantled disused sealed radioactive sources (DSRS), and low-level wastes measured the highest dose rate of 1.06 ± 0.92 µSv·h^-1. The range of the mean annual average personnel dose equivalent is 0.41-2.07 mSv. The annual effective doses are below the ICRP limit of 20 mSv. From the multivariate principal component analysis biplot, all the personal dose equivalent formed a cluster, and the cluster is mostly influenced by the radiological data from the outer wall surface of the facility where no DSRS are stored. The personal dose equivalents are not primarily due to the radiation exposures of staff during operations with DSRS at the facility but can be attributed to environmental radiation, thus the current radiation protection measures at the Facility can be deemed as effective.

• 한국산업보건학회지
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• 제31권3호
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• pp.226-236
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• 2021

Objectives: Concerns have been raised about the possible health effects of radon on both workers and consumers with the spread of social attention to the impact of radon exposure. Thus, an entire raw material handling workshop was investigated, and standards for radon levels in the workplace were newly established at 600 Bq/m³. However, regulations on the management of workers exposed to radon are still insufficiently developed. Therefore, by comparative analysis of overseas and domestic radon-related regulations for workplaces, this study aims to suggest improvement plans of protection regulations under the Occupational Safety and Health Act (OSH Act) for the prevention of health disorders of radon-exposed workers. Methods: For overseas case studies, we consulted radon-related laws and reports officially published on the websites of the European Union (EU), the United States (U.S.) and the United Kingdom (UK) government agencies. Domestic law studies were conducted mainly on the Act on Protective Action Guidelines against Radiation in the Natural Environment and the OSH Act. Results: In Europe, the basic safety standards for protection against risks arising from radon (Council Directive 2013/59/EURATOM of 5 December 2013) was established by the EU. They recommend that the Member States manage radon level in workplaces based on this criterion. In the U.S., the standards for workplaces are controlled by the Occupational Safety and Health Administration (OSHA) and the Mine Safety and Health Administration (MSHA). Action on radon in the UK is specified in "Radon in the workplace" published by the Health and Safety Executive (HSE). Conclusions: The Act on Protective Action Guidelines against Radiation in the Natural Environment mainly refers to the management of workplaces that use or handle raw materials but does not have any provisions in terms of protecting naturally exposed workers. In the OSH Act, it is necessary to define whether radon is included in radiation for that reason that its current regulations have limitations in ensuring the safety workers who may be exposed to naturally occurring radon. The management standards are needed for workplaces that do not directly deal with radon but are likely to be exposed to radon. We propose that this could be specified in the regulations for the prevention of health damage caused by radiation, not in Article 125 of the OSH Act.

• 핵의학기술
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• 제27권1호
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• pp.66-70
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• 2023

Purpose It is intended to improve the management efficiency of personal dosimeters by analyzing and sharing personal dosimeter loss cases and loss prevention measures. Materials and Methods From 2017 to 2021, data on the number of lost personal dosimeters were collected at large hospitals, and the number of personal dosimeters issued and lost were investigated. Results In order to prevent loss by institution, methods such as the use of auxiliary rings, contact stickers and dosimeter necklaces were implemented. Conclusion Hospitals are a business that frequently changes clothes, such as surgical gowns and work clothes, so there is a lot of loss. In addition, it was confirmed that the loss rate increases as the number of personal dosimeters issued increases.