• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.81-87
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• 2020

Background: Kori unit #1 is permanently shut down after a 40-year lifetime. The Nuclear Safety and Security Commission recommends establishing initial decommissioning plans for all nuclear and radwaste treatment facilities. Therefore, the Korea Atomic Energy Research Institute (KAERI) must establish an initial and final decommissioning plan for radwaste-treatment facilities. Radiation safety assessment, which constitutes one chapter of the decommissioning plan, is important for establishing a decommissioning schedule, a strategy, and cost. It is also a critical issue for the government and public to understand. Materials and Methods: This study provides a method for assessing external radiation dose to workers during decommissioning. An external dose is calculated following each exposure scenario, decommissioning strategy, and working schedule. In this study, exposure dose is evaluated using the deterministic method. Physical characterization of the facility is obtained by both direct measurement and analysis of the drawings, and radiological characterization is analyzed using the annual report of KAERI, which measures the ambient dose every month. Results and Discussion: External doses are calculated at each stage of a decommissioning strategy and found to increase with each successive stage. The maximum external dose was evaluated to be 397.06 man-mSv when working in liquid-waste storage. To satisfy the regulations, working period and manpower must be managed. In this study, average and cumulative exposure doses were calculated for three cases, and the average exposure dose was found to be about 17 mSv/yr in all the cases. Conclusion: For the three cases presented, the average exposure dose is well below the annual maximum effective dose restriction imposed by the international and domestic regulations. Working period and manpower greatly affect the cost and entire decommissioning plan; hence, the chosen option must take account of these factors with due consideration of worker safety.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2014년도 춘계학술대회
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• pp.489-492
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• 2014

본 논문에서는 컴퓨터 단층활영(CT)을 통해 발생되는 방사선 노출량의 관리를 위한 시스템의 소프트웨어 설계를 제안한다. 방사선 피폭량은 환자의 각 신체 부위별로 민감성의 차이에 따라 다르기 때문에 방사선의 노출량을 관리할 수 있게 되면 결과적으로 환자의 방사선 피폭량을 추정할 수 있다. 최근 일본 원전의 방사선 누출 사건이 국제적으로 뉴스가 되었고 원전 뿐 만아니라 의료용 방사선 피폭까지 폭넓게 관심이 커지고 있다. 현재 방사선 안전관리는 방사선 관계 종사자에 대해서만 관리되고 있지만, 이제는 환자에 대한 피폭 관리까지 요구되고 있다. 우리나라에서 방사선을 이용한 검사와 시술이 증가하여 이에 따른 의료 피폭이 증가하였으나 의료 기관에서는 환자에게 가해지는 방사선 피폭 수치를 알지 못하는 실정이다. 따라서 의료 기관에서 환자의 방사선 피폭을 관리할 수 있는 시스템이 필요하다. 본 논문에서는 의료 기관에서 방사선을 이용하는 대표적인 촬영 도구인 CT의 방사선 노출량을 관리할 수 있는 소프트웨어 설계를 제시한다. 방사선의 노출량을 확인하고 선량의 한도를 설정함으로써 환자의 의료 피폭량을 최적화 하는데 도움이 되고자 한다.

• 한국방사선학회논문지
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• 제16권3호
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• pp.357-363
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• 2022

본 연구 목적은 방사선관계종사자와 방사선작업종사자들의 직종별 방사선 피폭선량을 분석하여 폐 부작용 유발확률을 연구하는 데에 있다. 즉, 피폭관리 실태를 점검함으로써 방사선종사자들의 직업상 피폭에 대한 안전 점검 의식을 향상시키고 방사선안전관리에 도움을 주고자 한다. 방사선관계종사자와 방사선작업종사자 각각 3개의 직종별 (방사선사, 의사, 간호사)로 분류하였다. 피폭선량으로 인한 폐의 부작용 유발확률을 산출하기 위하여 ICRP103에 근거한 명목위험계수(Nominal risk factor)를 활용하였다. 방사선관계종사자의 1년간 심부선량은 방사선사 1.63 ± 2.84 mSv, 의사는 0.12 ± 0.22 mSv, 간호사는 0.59 ± 1.08 mSv로 나타났다. 이로 인하여, 폐의 부작용 유발 확률은 방사선사는 100,000당 1.1명, 의사는 10.082명, 간호사는 0.4명으로 나타났다. 방사선작업종사자의 1년간 심부선량은 방사선사 2.44 ± 3.30 mSv, 의사의 경우 0.19 ± 0.26 mSv, 간호사의 경우 0.12 ± 0.00 mSv이었다. 이 선량으로 인하여, 폐의 부작용 유발 확률은 방사선사는 100,000당 1.2명, 의사는 0.096명, 간호사는 0.06명으로 나타났다. 본 연구에서는 방사선 피폭선량의 직종별 폐에 부작용이 발생할 확률을 연구하여 향후 확률적 영향과 관련하여 방사선 안전관리를 위하여 유용한 자료로 활용될 것으로 사료된다.

• 디지털콘텐츠학회 논문지
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• 제13권3호
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• pp.421-429
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• 2012

최근 방사선 의료에서 중재적 시술의 확대로 인하여 시술 건수가 증가하고 있으며, 시술자에 따라 방사선 노출이 다르게 나타 날 수 있으며 시술자와 환자가 받는 방사선 피폭의 증가를 가져온다. 본 연구는 2011년 11월 01일부터 2012년 01월 31일 까지 경북지역 S대학 병원에 내원한 303명의 심장내과 환자를 대상으로 중재적 방사선시술을 시행한 시술자 5명에 따른 방사선 노출특성을 비교분석하였다. 투시시간의 경우 5명의 시술의의 평균 투시시간은 697.95초, cumulative DAP(exp)의 경우 평균 환자 면적선량은 $52,730mGycm^2$, total DAP의 경우 평균 환자면적선량은 $104,875.14mGycm^2$, acquired image의 경우 평균 영상은 855.52frame, exposure image의 평균 영상은 802.2frame로 나타나 통계적으로 유의한 차이를 보였다(p<0.05). 장비의 X선 노출 특성 즉, 투시시간, cumulative DAP(fluro), cumulative DAP(exp), total DAP, acquired image, exposure image는 서로 높은 상관관계를 보이나 cumulative DAP(exp)와 acquired runs는 상관관계를 보이지 않았다. 시술자와 가장 큰 비중을 차지하는 것은 투시시간으로 나타나 투시시간이 길어질수록 방사선 피폭이 증가함을 의미한다. 시술시 피폭선량은 시술자에 따라 시술능력과 경험, 시술의 난이도 및 정밀 시술여부와 관련 있으며, 혈관 조영의 횟수와 투시시간이 정해진 것이 아니어서 인위적인 조절이 어려운 부분이라 할 수 있다. 따라서, 중재방사선 절차를 수행하는 의료진의 실질 피폭을 합리적으로 평가하는 시스템이 필요하며, 불필요한 피폭을 줄이기 위해 시술자를 비롯한 방사선 작업종사자에 대한 자체교육과 훈련이 필요할 것으로 사료된다.

• 한국의학물리학회지:의학물리
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• 제27권3호
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• pp.146-155
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• 2016

As the probability of exposure to radiation increases due to an increase in the use of radioisotopes and radiation generators, the importance of a radiation safety management field is being highlighted. We intend to help radiation workers with exposure management by identifying the degree of radiation exposure and contamination to determine an efficient method of radiation safety management. The personal exposure doses of the radiation workers at the Korea Institute of Radiological & Medical Sciences measured every quarter during a five-year period from Jan. 1, 2011 till Dec. 31, 2015 were analyzed using a TLD (thermoluminescence dosimeter). The spatial dose rates of radiation-controlled areas were measured using a portable radioscope, and the level of surface contamination was measured at weekly intervals using a piece of smear paper and a low background alpha/beta counter. Though the averages of the depth doses and the surface doses in 2012 increased from those in 2011 by about 14%, the averages were shown to have decreased every year after that. The exposure dose of 27 mSv in 2012 increased from that in 2011 in radiopharmaceutical laboratories and, in the case of the spatial dose rate, the rate of decrease in 2012 was shown to be similar to the annual trend of the whole institute. In the case of the surface contamination level, as the remaining radiation-controlled area with the exception of the I-131 treatment ward showed a low value less than $1.0kBq/m^2$, the annual trend of the I-131 treatment ward was shown to be similar to that of the entire institute. In conclusion, continuous attention should be paid to dose monitoring of the radiation-controlled areas where unsealed sources are handled and the workers therein.

• Journal of Ecology and Environment
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• 제37권4호
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• pp.195-200
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• 2014

The chances of accidental exposure are augmented as the application of ionizing radiation increases in various fields. Such accidental exposures may occur at nuclear power plants, laboratories, and hospitals. Cytogenetic assays have been used for estimating radiation dose in the situation of the accidents. The micronucleus assay has several advantages over the other cytogenetic methods as it is simple and fast. The present study aimed at investigation of the micronuclei frequencies in cytokinesis-block cells in human blood lymphocytes after ${\gamma}$-irradiation and at establishment of a standard dose response relationship. The samples of peripheral blood were obtained from 6 different donors aged between 24 and 30 years old. The bloods were irradiated in vitro with 0-5 Gy. A linear quadratic dose-response equation was obtained by scoring the micronuclei in binucleated cells; $y=27.87x^2+46.13x+2.08$ ($r^2=0.99$). Irradiation caused a significant decrease in the nuclear division index. Necrotic and apoptotic cells increased in number after irradiation in a dose-dependent manner. In conclusion, the conventional cytokinesis-block micronucleus assay has proven to be the great technique in biological dosimetry. Dose-response calibration curve derived from CMBN assay could be used to estimate the exposure dose during a radiological emergency.

• 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.

• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2011년도 추계학술대회
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• pp.563-571
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• 2011

The purpose of the study was to evaluation of the radiation dose reduction using various automatic exposure control (AEC) systems in different manufactures multi-detector computed tomography (MDCT). We used three different manufacturers for the study: General Electric Healthcare, Philips Medical systems and Siemens Medical Solutions. The general scanning protocol was created for the each examination with the same scanning parameters as many as possible. In the various AEC systems, the evaluation of reduced-dose was evaluated by comparing to fixed mAs with using body phantom. Finally, when we applied to AEC for three manufacturers, the radiation dose reduction decreased each 35.3% in the GE, 58.2% in the Philips, and 48.6% in the Siemens. This applies to variety of the AEC systems which will be very useful to reduce the dose and to maintain the high quality.

• 한국콘텐츠학회논문지
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• 제14권11호
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• pp.864-870
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• 2014

선량계 유용성을 평가하기 위한 방법으로 방사선관계종사자의 피폭선량을 측정하여 개인피폭관리를 위한 선량계 선택의 기초 자료를 제시하고자 하였다. 2012년 1년간 방사선사 30명을 대상으로 하였으며 개인피폭 누적선량을 측정하여 열형광선량계, 형광유리선량계, 광자극발광선량계의 성능을 조사하였다. 연구방법으로는 DAP와 ion-chamber를 이용하여 세종류 개인피폭선량계의 선량측정값을 비교 분석하였으며 의료기관별, 검사업무별, 분기별 방사선관계종사자의 피폭누적선량을 확인하였다. 결과적으로 직접 X선조사를 통한 개인피폭선량계의 선량값과 ion-chamber의 절대값에서 광자극발광선량계가 열형광선량계나 형광유리선량계에 비해 더 유사한 선량값을 나타내 측정 능력면에서 더 우수한 결과를 나타냈다. 또한 방사선발생구역에서 방사선관계종사자의 피폭선량이 광자극발광선량계에서 보다 높게 나타났다.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.424-435
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• 2016

Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.