• 방사선산업학회지
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• 제11권1호
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• pp.47-54
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• 2017

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a significant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4543-4553
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• 2023

The dose from a possible accident at a microwave-based spent resin mixture treatment facility that was to be installed and operated at the Wolsong nuclear power plant was analyzed to evaluate the radiological safety prior to its installation and operation. The dose to which workers and nearby residents are likely to be exposed was calculated based on the atmospheric dispersion and deposition factors using the XOQDOQ code. The highest atmospheric dispersion factors were 1.349E-05 s/m³ (workers) and 1.534E-06 s/m³ (residents). The highest doses due to emissions from the mock-up tank before operation were 1.91E-06 mSv (workers) and 1.78E-07 mSv (residents). Even after 3 h of operation, emissions from the mock-up tank had the greatest impact ranging from 4.63E-08 to 1.24E-06 mSv (workers) and 2.74E-10 to 1.16E-07 mSv (residents), respectively. The doses were 7.09E-09-4.55E-07 mSv and 4.18E-11-4.25E-08 mSv at 4-5 h of operation, and the maximum doses after operation reached 5.69E-07 mSv and 5.31E-08 mSv for the workers and residents, respectively. Even at the exclusion area boundary (EAB), 4.76E-08-9.51E-07 mSv (annual dose:9.52E-05–1.90E-03 mSv/y) was below the dose limit of the EAB, and the safety of the facility installation inside the NPP was confirmed.

• 한국방사선학회논문지
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• 제15권3호
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• pp.355-359
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• 2021

본 연구에서는 교내 실습 중 방사선(학)과 에 지정된 방사선작업종사자 및 수시출입자의 피폭 정도를 분석하여 방사선(학)과에 대한 원자력안전법의 방사선 방호에 대한 타당성과 최적화에 대한 기초 연구에 목적을 두었다. 연도별 작업종사자의 평균 피폭선량 2014년과 2016년에 0.01 mSv로 가장 낮은 수치가 나타났으며. 가장 높은 수치는 2018년도로 0.12 mSv이다. 연도별 수시출입자의 평균 피폭선량은 2018년 0.013 mSv로 가장 낮은 수치를 보였으며, 2016년 0.022 mSv로 가장 높은 수치가 나타났다. 본 연구를 통하여 방사선 발생장치만을 사용하는 대학의 담당교수, 실습 조교 및 방사선(학)과의 학생들은 교내실습 과정에서 받는 연간 피폭선량은 일반인의 선량한도인 1mSv에도 미치지 못하는 수준이다. 그러므로 방사선(학)과 학생들의 피폭선량이 일반인의 선량한도 보다 낮게 나오는 시점에서 현재 원자력안전법의 안전규제는 과도한 규제라고 판단된다. 따라서 현재의 원자력안전법에서 방사선 발생장치의 규정을 개정하거나 대학의 재학생에 대한 방사선안전관리 체계를 수정하는 것은 필요하다고 사료된다.

• 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.

• Environmental Analysis Health and Toxicology
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• 제31권
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• pp.7.1-7.6
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• 2016

Objectives The aim of this study is to evaluate radiation exposure resulting from the comprehensive health examinations of selected university hospital programs and to present basic data for research and management strategies on the health effects of medical radiation exposure. Methods Radiation-based diagnostic studies of the comprehensive health examination programs of ten university hospitals in Seoul, Korea, as introduced in their websites, were analyzed. The medical radiation studies of the programs were reviewed by radiologists. Only the effective doses of the basic studies were included in the analysis. The optional studies of the programs were excluded. Results Among the 190 comprehensive health examination programs, 132 programs (69.5%) included computed tomography studies, with an average of 1.4 scans. The average effective dose of radiation by program was 3.62 mSv for an intensive program for specific diseases; 11.12 mSv for an intensive program for cancer; 18.14 mSv for a premium program; and 24.08 mSv for an overnight program. A higher cost of a programs was linked to a higher effective dose (r=0.812). The effective doses of the examination programs for the same purposes differed by as much as 2.1 times by hospital. Inclusion of positron emission tomography-computed tomography was the most critical factor in determining the level of effective dose. Conclusions It was found that radiation exposure dose from comprehensive health exam programs targeted for an asymptomatic, healthy public reached between 3.6 and 24 times the annual dose limit for the general public. Relevant management policies at the national level should be provided to minimize medical radiation exposure.

• 대한방사선기술학회지:방사선기술과학
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• 제45권2호
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• pp.159-164
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• 2022

The study developed a radiation dose measurement program in the radiology laboratory to measure how much exposure the students are exposed to during the radiology class, to request for the improvement and the revision of the current Nuclear Safety Act. The experimental program is shown in the following figure, and experiments were conducted to determine the degree of radiation exposure in the control room with a lead gown at a distance of 1 m, 2 m, and 1 m, and in a control room with a radiographic lead glass wall. The duration of the experiment was 3 months from April to June, when radiation imaging practice classes were conducted, and 128 hours of imaging practice per month were conducted. In order to find out the dose of radiation dose during radiology imaging practice class, the experiment was carried out from April to June for 3 months, and according to the program, the results of exposure dose were 0.34 mSv at 1 m distance, 0.01 mSv at shielding of lead gown at 1 m distance, 0.16 mSv at 2 m distance, and 0.01 mSv at control room with radiation lead glass wall. The exposure dose from the test results was much below the annual general public limit dose of 1 mSv. The restriction on the operation of the radiation equipment in the practice of the students is a regulation that infringes the right of students to learn, and amendments or exemptions of Nuclear Safety Act should be enacted to ensure that it does not violate the fundamental right to learn for students in radiology.

• 대한방사선기술학회지:방사선기술과학
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• 제44권5호
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• pp.489-494
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• 2021

In this study, radioactivity quantitative analysis was performed on radon contained in cigarette, and the effective dose was calculated using the result value to determine the amount of exposure caused by smoking. A total of 5 types of cigarettes were sampled. Cigarette smoke was collected by using activated carbon, and tobacco were measured by homogenizing for quantitative analysis. For each sample, Bi-214 and Pb-214 were subjected to gamma nuclide analysis to observe the uranium-based radioactive material contained in cigarette, and a measurement time of 30,000 seconds was set for the sample based on the results of previous studies. As a result of measuring the radioactivity of tobacco, a maximum of 0.715 Bq/kg was derived, and in the case of cigarette smoke measured using activated carbon, a maximum of 3.652 Bq/kg was derived. Using this measurement, the average effective dose to the lungs is 0.938 mSv/y, and it was found that there is a possibility of receiving exposure up to 1.099 mSv/y depending on the type of tobacco. It was found that the exposure dose due to cigarette occupies a large proportion of the annual effective dose limit for the general public. Therefore, more diverse studies on radioactive substances in cigarette are needed, and measures to monitor and reduce the incidental exposure to radon should be established.

• Journal of Radiation Protection and Research
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• 제46권2호
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• pp.58-65
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• 2021

Background: The evaluation of skyshine distribution, release of airborne radioactive nuclides, and soil activation and groundwater migration were required for radiological assessment of the impact on the environment surrounding In-Flight (IF)-system facility of the RAON (Rare isotope Accelerator complex for ON-line experiment) accelerator complex. Materials and Methods: Monte Carlo simulation by MCNPX code was used for evaluation of skyshine and activation analysis for air and soil. The concentration model was applied in the estimation of the groundwater migration of radionuclides in soil. Results and Discussion: The skyshine dose rates at 1 km from the facility were evaluated as 1.62 × 10^-3 μSv·hr^-1. The annual releases of ³H and ¹⁴C were calculated as 9.62 × 10^-5 mg and 1.19 × 10^-1 mg, respectively. The concentrations of ³H and ²²Na in drinking water were estimated as 1.22 × 10^-1 Bq·cm^-3 and 8.25 × 10^-3 Bq·cm^-3, respectively. Conclusion: Radiological assessment of environmental impact on the IF-facility of RAON was performed through evaluation of skyshine dose distribution, evaluation of annual emission of long-lived radionuclides in the air and estimation of soil activation and groundwater migration of radionuclides. As a result, much lower exposure than the limit value for the public, 1 mSv·yr^-1, is expected during operation of the IF-facility.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.3046-3053
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• 2023

Radon is a naturally occurring carcinogenic agent, poses a serious health hazard when inhaled or ingested in significant amounts. The water of the Padma river will be used as a tertiary coolant for the soon-to-be-commissioned 'Rooppur Nuclear Power Plant'. Hence, it is important to assess the radiological status of the river prior to the commission of this power plant. Therefore, for the first time, 25 samples of water were collected from various locations of the Padma River and analyzed for radon concentration using the RAD H₂O (DURRIDGE) radon monitoring device. The radon concentrations were found in the range from 0.077 ± 0.036 to 0.494 ± 0.211 Bq/L with a mean of 0.250 ± 0.093 Bq/L. All the concentrations were found to be below the recommended limits of WHO (100 Bq/L) and USEPA (11.1 Bq/L). The mean annual effective dose due to the radon exposure via inhalation and ingestion pathways were 0.638 µSv/y and 0.629 µSv/y, respectively, which were all well below the annual effective dose recommended by WHO (0.1 mSv/y). Since Bangladesh lacks a national safety limit of radon in water, this pioneering study provides baseline data on radon levels for the environment around Rooppur Nuclear Power Plant.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.299-303
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• 2001

Using ultrasound techniques, the Korea Atomic Energy Research Institute has measured chest wall thicknesses of a group of male workers at the Korea Atomic Energy Research Institute. A site-specific biometric equation has been developed for these workers. Chest wall thickness is an important modifier on lung counting efficiency. These data have been put into the perspective of the ICRP recommended dose limits for occupationally exposed workers: 100 mSv in a 5-year period with a maximum of 50 mSv in anyone year. For measured chest wall thicknesses of 1.9 cm to 4.1 cm and a 30 min counting time, the achievable MDAs for natural uranium in the KAERI lung counter vary from 5.75 mg to 11.28 mg. These values are close to, or even exceed, the predicted amounts of natural uranium that will remain in the lung (absorption type M and S) after an intake equal to the Annual Limit on Intake corresponding to a committed dose of 20 mSv. This paper shows that the KAERI lung counter probably cannot detect an intake of Type S natural uranium in a worker with a chest wall thickness equal to the average value (2.7 cm) under routine counting conditions.