• Journal of Radiation Protection and Research
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• 제46권4호
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• pp.213-217
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• 2021

Background: Radiation exposure can occur as a result of occupational activities utilizing sources of radiation. The average level of occupational exposure is generally similar to the global average, but some workers receive more than this. In this study, the occupational exposure data for workers in Korea to check the recent trend of radiation exposure. Materials and Methods: The data collection and analysis are carried out by two separate periods based on the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) survey. One is the year 2003 to 2014 for a recent survey, and the other is 2015 to 2019. All available data were collected by annual reports from radiation dose registry organizations. Results and Discussion: The annual dose over the record level to the total workers did not change much compared with the total increasing number of workers in this period. The dose to the nuclear fuel cycle field has a tendency to decrease. It resulted from the efforts of radiation dose reduction with high technology introduced to this area. Also, it is important result that the radiation dose to the workers in radiography is remarkably reduced. Conclusion: The number of radiation workers and average doses were analyzed for occupational categories in Korea. It still needs cooperative efforts between the dose registry organizations for the efficient dose management of Korean radiation workers.

• 한국방사선학회논문지
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• 제11권5호
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• pp.321-328
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• 2017

D-Shuttle (Chiyoda Technol Corporation, Tokyo, Japan) 선량계를 이용하여 개인피폭관리 및 자연방사선량의 모니터링을 위한 기초자료를 제공하는데 연구의 목적이 있다. D-Shuttle을 이용하여 선량을 산출하였다. 선량보고서에서 400 일 노출되었을 때에 1.346 mSv 이었고, 연간선량 (annual dose per year)은 1.228 mSv/year, 평균시간선량 (average dose per hour)은 $0.014{\mu}Sv/hr$ 이었다. 국내의 개인 외부피폭선량 (1.295 mSv/year =Korea average natural individual external dose), 국내의 연간부가선량 (additional dose per year)은 -0.0663 mSv/year 이다. D-Shuttle은 방사선모니터링을 위한 개인선량계로 방사선의 검출성능 우수한 기능, 실시간 방사선 피폭관리, 방사선 작업의 경보 기능, 효율적이고 사용이 편리한 개인 방사선선량의 피폭관리로 ALARA에 매우 유용한 선량계로 사용할 수 있다. 방사선작업종사자와 지역주민의 방사선모니터링 측정기기로 병원, 산업, 의료현장, 원전사고 지역과 비파괴 분야의 위험한 지역에서 방사선모니터링으로 활용될 수 있다.

• Journal of Radiation Protection and Research
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• 제42권4호
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• pp.222-228
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• 2017

Background: On June 18, 2017, Korea's first commercial nuclear reactor, the Kori Nuclear Power Plant No. 1, was permanently suspended, and the capacity of nuclear power generation facilities will be adjusted according to the governments denuclearization policy. In these circumstances, it is necessary to assess the quality of radiation safety management in nuclear power plants in Korea by evaluating the radiation dose associated with them. Materials and Methods: The average annual radiation dose per unit, the annual radiation dose per person, and the annual dose distribution were analyzed using the radiation dose database of nuclear reactors for the last 5 years. The results of our analysis were compared to the specifications of the Nuclear Safety Act and Medical Law in Korea. Results and Discussion: The annual average per unit radiation dose of global major nuclear power generation was 720 man-mSv, while that of Korea's nuclear power plants was 374 manmSv. No workers exceeded 50 mSv per year or 100 mSv in 5 years. The individual radiation dose according to occupational exposure was 0.59 mSv for nuclear workers, 1.77 mSv for non-destructive workers, and 0.8 mSv for diagnostic radiologists. Conclusion: The radiation safety management of nuclear power plants in Korea has achieved the best outcomes worldwide, which is considered to be the result of the as-low-as-reasonably-achievable (ALARA) approach and strict radiation safety management. Moreover, the occupational exposures were also very low.

• Journal of Radiation Protection and Research
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• 제37권4호
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• pp.231-236
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• 2012

This study derived measures to reduce exposure doses by identifying factors which affect the external radiation dose rate of patients treated with radiopharmaceuticals for PET-CT tests. The external radiation dose rates were measured on three parts of head, thorax and abdomen at a distance of 50cm from the surface of 60 PET-CT patients. It showed there are changes in factors affecting the external radiation dose rate over time after the administration of F-18 FDG. The external radiation dose rate was lower in the patients with more water intake than those with less water intake before the injection of radiopharmaceuticals at all three points: right after the injection of radiopharmaceuticals (average 4.17 mins), after the pre-PEET-CT urination step (average 77.47 mins), and right after the PET-CT test (average 114.15 mins). The study also found there is a need to increase the amount of water intake before the injection of radiopharmaceuticals in order to maintain a low external radiation dose rate in patients. This strategy is only possible under the assumption that the quality of the video has not changed after conducting this study on the relations between the image and quality. This study also found a need to use radiopharmaceuticals with the minimum amount needed for each patient because F-FDG doses affects the external radiation dose rate at the point right after the injection of radiopharmaceuticals. Urination frequency was the most significant factor to affect the external radiation dose rates at the point right after the PET-CT test and the point after the pre-PET-CT urination step. There is a need to realize the strategy to increase the urination frequency of patients to maintain the external radiation dose rate low (average 77.47 mins) before and after the injection of radiopharmaceuticals. In addition, at this point, there is a need to take advantage of personal strategies because the external radiation dose rate is lower if the fasting time is shorter, the contrast medium is used, and the amount of water intake is increased after the administration of radiopharmaceuticals. Finally this study found the need to be able to generalize these findings through an in-depth research on the factors affecting the external radiation dose rate, which includes radiopharmaceutical dose, urination frequency, the amount of water intake, fasting time and the use of contrast medium.

• 방사선산업학회지
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• 제17권1호
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• pp.61-67
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• 2023

A Study on the Introduction of Dose Constraints for Occupational Exposures: Focusing on Experts' Opinions by Field of Radiation Industry. The International Commission on Radiological Protection suggests Justification, Optimization, and Dose Limits as the three principles of radiological protection, among which, as a means of protection optimization, ICRP 103 recommends to set dose constraints. In this study, opinions are collected from experts in each category of radiation industries for stakeholder participation to qualify dose constraints. A guidance and questionnaire for analyzing the dose constraints have been developed for their collection, and opinions were collected from radiation protection experts in selected categories. 20 out of 22 experts, consisted with 91%, have assessed the dose constraints setting is necessary, and 2 experts, consisted with 9%, assessed it is unnecessary. The average of dose constraint presented by experts for RI production institutions is to be the highest level of 15.3 mSv, and light-water reactors (14.6 mSv), non-destructive inspection (14.4 mSv), heavy-water reactor and medical institutes (13.9mSv) is to be above the overall average dose constraint. In case of public institutions, the average dose constraint is to be 8.6mSv, and research institutions (8.8mSv), educational institutions (9.6 mSv), waste disposal sites (9.7 mSv), and general industries (10.6 mSv) are resulted to below the overall average dose constraint. As for the means of setting dose constraints, 8 experts out of 22 suggested setting dose constraints for each specific industry or task. And, 5 experts especially suggest setting dose constraints for the specific groups with relatively high exposure, such as workers with above the record levels. As a countermeasure for workers who exceed the dose constraints, 15 experts out of 22 expressed that the cause analyses for them and preparation for a plan of reducing them are necessary.

• 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.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2004년도 학술대회 논문집 정보 및 제어부문
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• pp.319-321
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• 2004

The average glandular dose (AGD) is determined by the breast entrance skin exposure, x-ray tube target material, beam quality (half-value layer), breast thickness, and breast composition. Almost breast cancer always arises in glandular breast tissue. As a result, the average radiation absorbed dose to glandular tissue is the preferred measure of the radiation risk associated with mammography. If the normalized average glandular dose is known, the average glandular dose can be computed from the product of the normalized average glandular dose and breast entrance skin exposure. In this study, AGD was calculated by the breast thickness and various x-ray energy (HVL) in 50% glandular 50% adipose breast by Mo.-Rh. assembly. AGD is 84 mrad in compressed 5 cm breast. These results show that as increasing the breast thickness, dose also increases. But as increasing the x-ray tube voltage, dose decreases because of high penetrating ratio through the object. But high tube voltage is reducing the subject contrast. From this result, we have to consider the trade-off between subject contrast of image and dose to the patient and choose proper x-ray energy range.

• 대한방사선기술학회지:방사선기술과학
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• 제30권3호
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• pp.213-219
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• 2007

중재적 시술의 시술자를 대상으로 방사선 방호용구의 안과 밖의 실제 방사선량을 측정하여 이를 바탕으로 방사선 방호용구의 방사선 차폐율을 비교 분석하는 것이다. 2005년 5월부터 9월까지 중재적 시술 중에서 시행 빈도가 높은 TACE, PTBD를 시행하는 중재적 시술자 4인에게 방사선 방호용구의 착용 시 피폭선량 감쇄효과를 측정하기 위해 각 신체부위별 방호용구 안과 밖에 TLD를 부착하여 피폭선량을 측정하였다. TLD 부착부위는 Goggle inside, Goggle outside, Thyroid protector inside, Thyroid protector outside, Apron inside(waist level), Apron outside(upper chest level), Hand 4th finger(ring type TLD)와 환경방사선을 측정하기 위해 TLD 10개를 Control room 여러 곳에 위치시켰다. TACE 검사시 0.07 mmPb Goggle의 사용으로 연속투시방식에서는 평균 53.8%의 선량율감쇄를 보였으며 펄스투시방식에서는 77.6%의 감쇄효과를 보였고, 0.5 mmPb Thyroid protector의 사용에서는 연속투시방식에서는 평균 88.9%의 선량율감쇄를 보였으며 펄스투시방식에서는 92.8%로 선량율감쇄에서는 유의한 차이가 없었다. PTBD 검사시 0.07 mmPb Goggle의 사용으로 평균 62.7%의 선량율감쇄를 보였으며, 0.5 mmPb Thyroid protector의 사용에서는 평균 89.1% 선량율이 감쇄 되었고 0.5 mmPb Apron의 사용에서도 평균 87.9%의 감쇄효과가 있었다. PTBD 시술은 TACE 시술에 비해 평균 투시시간은 6.14 min이나 적었으나 피폭선량은 체부에서 약 3배, 손에서는 40배 이상 피폭되었다. 납당량이 두꺼운 방호용구를 착용하거나 최소한 권고되어지는 0.5 mmPb 이상의 것을 착용하여야 하며, 시술시 눈을 보호하는 Goggle의 착용을 생활화해야 한다. 테이블 아래쪽에 납커튼을 장착하면 복부의 피폭선량율은 평균 38.4% 감쇄하므로 납커튼을 장착하여 산란선을 차폐하여야 한다. 펄스투시방식을 이용하면 연속투시에 비해 피폭선량율이 평균 59.0% 감쇄되므로 연속투시보다 펄스투시방식을 선택하여 피폭선량을 감소시켜야 한다.

• 핵의학기술
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• 제14권2호
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• pp.9-16
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• 2010

본 연구는 방사성동위원소의 의학적 이용도가 증가함에 따라 의료기관 핵의학과 방사선 관계종사자의 직무 별 방사선 이용에 대한 개인 방사선 피폭선량의 실태를 파악하여, 방사선 위험에 대해 경각심을 고취시키고, 방사선 관계종사자들에게 안전관리와 합리적인 피폭선량 관리에 도움을 주고자 분석하였다. 2007년 1월 1일부터 2009년 12월 31일까지 의료기관에서 근무하는 핵의학 방사선 관계종사자로 분류되어 개인 방사선피폭선량 측정을 정기적, 연속적으로 3년 간 조사 관리된 40명의 종사자를 대상으로 직종 별, 영상실 별, 연령 별, 선량구간 별, 직무 별 관련업무를 파악하여 심부선량에 대하여 연간평균피폭선량을 각각 분석하였다. 분석법으로는 빈도분석과 ANOVA를 시행하였다. 3년 간 영상실 별 연간피폭선량은 PET 및 PET/CT 영상실이 11.06~12.62 mSv로 가장 높은 피폭선량을 보였고, 감마카메라 주사실이 11.72 mSv로 높았으며, 직종 별 연간평균피폭선량은 임상병리사가 8.92 mSv로 가장 높았고, 방사선사 7.50 mSv, 간호사 2.61 mSv, 연구원 0.69 mSv, 접수 0.48 mSv, 의사 0.35 mSv 순으로 나타났으며, 세부업무에 따른 직무별 연간평균피폭선량은 PET 및 PET/CT 업무가 12.09 mSv로 가장 높은 피폭선량을 보였으며, 감마카메라 주사실이 11.72 mSv, 싸이크로트론 관련 합성 업무 8.92 mSv, 감마카메라 영상업무 4.92 mSv, 치료 및 안전관리 2.98 mSv, 간호사 업무 2.96 mSv, 관리 업무 1.72 mSv, 영상분석 업무 0.92 mSv, 판독업무 0.54 mSv, 접수업무 0.51 mSv, 연구업무 0.29 mSv 순으로 나타났다. 선량구간 별 연간평균피폭선량은 연구대상자의 15명(37.5%)이 1 mSv이하의 선량분포와 5명(12.5%)이 1.01~5.0 mSv이하의 선량분포를 가지고 있었고, 5.01~10.0mSv에서 14명(35.0%), 10.01~20.0 mSv에서 6명(15.0%)의 분포로 분석되었다. 연령에 따른 연간평균피폭선량은 방사선사 직종에서는 25~34세 종사자가 8.69 mSv로 가장 높은 평균선량을 보였고, 근무기간에 따른 연간평균피폭선량은 방사선사 직종에서 5~9년 종사자가 9.5 mSv로 가장 높은 평균선량을 나타냈다. 고용형태에 따른 연간평균피폭선량은 정규직 임상병리사 8.92 mSv, 방사선사 7.82 mSv, 계약직 방사선사 7.55 mSv, 인턴직 방사선사 5.62 mSv, 계약직 간호사 2.61 mSv, 정규직 연구원 0.69 mSv, 접수 0.55 mSv, 의사 0.35mSv 순으로 피폭을 받는 것으로 나타났다. 이와 같은 결과로 볼 때 의료기관에서 근무하는 핵의학 방사선 관계종사자의 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 합리적 피폭량 관리를 위한 체계가 필요하다고 사료된다.

• 한국의학물리학회지:의학물리
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• 제30권4호
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• pp.120-127
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• 2019

Purpose: This study was designed to evaluate the dosimetric performance of Mobius3D by comparison with an aSi-based electronic portal imaging device (EPID) and Octavius 4D, which are conventionally used for patient-specific prescription dose verification. Methods: The study was conducted using nine patients who were treated by volumetric modulated arc therapy. To evaluate the feasibility of Mobius3D for prescription dose verification, we compared the QA results of Mobius3D to an aSi-based EPID and the Octavius 4D dose verification methods. The first was the comparison of the Mobius3D verification phantom dose, and the second was to gamma index analysis. Results: The percentage differences between the calculated point dose and measurements from a PTW31010 ion chamber were 1.6%±1.3%, 2.0%±0.8%, and 1.2%±1.2%, using collapsed cone convolution, an analytical anisotropic algorithm, and the AcurosXB algorithm respectively. The average difference was found to be 1.6%±0.3%. Additionally, in the case of using the PTW31014 ion chamber, the corresponding results were 2.0%±1.4%, 2.4%±2.1%, and 1.6%±2.5%, showing an average agreement within 2.0%±0.3%. Considering all the criteria, the Mobius3D result showed that the percentage dose difference from the EPID was within 0.46%±0.34% on average, and the percentage dose difference from Octavius 4D was within 3.14%±2.85% on average. Conclusions: We conclude that Mobius3D can be used interchangeably with phantom-based dosimetry systems, which are commonly used as patient-specific prescription dose verification tools, especially under the conditions of 3%/3 mm and 95% pass rate.