• 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.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.248-253
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• 2023

Directly, it is not possible to measure the absorbed dose of radiopharmaceuticals in the organs of the human body. Therefore, simulation methods are utilized to estimate the dose in distinct organs. In this study, individual organs were separately considered as the source organ or target organ to calculate the mean absorption dose, which SAF and S factors were then calculated according to the target uptake via MIRD method. Here, ^99mTc activity distribution within the target was analyzed using the definition and simulation of ideal organs by summing the fraction of cumulative activities of the heart as source organ. Thus, GATE code was utilized to simulate the Zubal humanoid phantom. To validate the outcomes in comparison to the similar results reported, the accumulation of activity in the main organs of the body was calculated at the moment of injection and cardiac rest condition after 60 min of injection. The results showed the highest dose absorbed into pancreas was about 21%, then gallbladder 18%, kidney 16%, spleen 15%, heart 8%, liver 8%, thyroid 7%, lungs 5% and brain 2%, respectively, after 1 h of injection. This distinct simulation model may also be used for different periods after injection and modifying the prescribed dose.

• Environmental Analysis Health and Toxicology
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• 제31권
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• pp.1.1-1.13
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• 2016

Objectives To investigate the accuracy and scientific validity of the current very low risk factor for hereditary diseases in humans following exposures to ionizing radiation adopted by the United Nations Scientific Committee on the Effects of Atomic Radiation and the International Commission on Radiological Protection. The value is based on experiments on mice due to reportedly absent effects in the Japanese atomic bomb (A-bomb) survivors. Methods To review the published evidence for heritable effects after ionising radiation exposures particularly, but not restricted to, populations exposed to contamination from the Chernobyl accident and from atmospheric nuclear test fallout. To make a compilation of findings about early deaths, congenital malformations, Down's syndrome, cancer and other genetic effects observed in humans after the exposure of the parents. To also examine more closely the evidence from the Japanese A-bomb epidemiology and discuss its scientific validity. Results Nearly all types of hereditary defects were found at doses as low as one to 10 mSv. We discuss the clash between the current risk model and these observations on the basis of biological mechanism and assumptions about linear relationships between dose and effect in neonatal and foetal epidemiology. The evidence supports a dose response relationship which is non-linear and is either biphasic or supralinear (hogs-back) and largely either saturates or falls above 10 mSv. Conclusions We conclude that the current risk model for heritable effects of radiation is unsafe. The dose response relationship is non-linear with the greatest effects at the lowest doses. Using Chernobyl data we derive an excess relative risk for all malformations of 1.0 per 10 mSv cumulative dose. The safety of the Japanese A-bomb epidemiology is argued to be both scientifically and philosophically questionable owing to errors in the choice of control groups, omission of internal exposure effects and assumptions about linear dose response.

• Journal of Preventive Medicine and Public Health
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• 제33권2호
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• pp.165-173
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• 2000

Objectives : To assess the availability of the glycophorin A (GPA) assay to detect the biological effect of ionizing radiation in workers exposed to low-doses of radiation. Methods : Information on confounding factors, such as age and cigarette smoking was obtained on 144 nuclear power plant workers and 32 hospital workers, by a self-administered questionnaire. Information on physical exposure levels was obtained from the registries of radiation exposure monitoring and control at each facility. The GPA mutant assay was performed using the BR6 method with modification by using a FACScan flow cytometer. Results : As confounders, age and cigarette smoking habits showed increasing trends with GPA variants, but these were of no statistical significance. Hospital workers showed a higher frequency of the GPA variant than nuclear power plant workers in terms of the NO variant. Significant dose-response relationships were obtained from in simple and multiple linear regression models. The slope of the regression equation for nuclear power plant workers was much smaller than that of hospital workers. These findings suggest that there may be apparent dose-rate effects. Conclusion : In population exposed to chronic low-dose radiation, the GPA assay has a potential to be used as an effective biologic marker for assessing the bone marrow cumulative exposure dose.

• 한국방사선학회논문지
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• 제10권7호
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• pp.495-502
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• 2016

본 연구는 일개 종합병원 내 방사선 종사자의 피폭선량과 그에 따른 혈액검사를 일반인의 혈액검사결과와 비교하여 방사선피폭의 영향을 분석하였다. 대조군과 방사선 종사자군의 혈액검사 결과 모든 항목 평균 값은 정상범위에 포함되어 있었다. 호산구의 경우 방사선 종사자가($2.52{\pm}1.79%$) 대조군($2.92{\pm}1.39%$)에 비하여 낮으며 유의함을 나타내었다. 방사선 작업 종사기간에 따른 종사자군과 대조군의 혈액학적 검사결과 평균값은 백혈구, 혈소판, 임파구, 단핵구, 호염기구가 전체 평균에서 종사자군이 높은 값을 나타내었고, 20년 이상 종사자에서 대조군에 비하여 백혈구, 단핵구는 낮고, 혈소판은 높은 값을 나타내었으며, 10년 이하 종사자에서 호염기구가 대조군에 비해 낮은 값을 나타내었으나 전체 수치의 통계적 유의성은 없었다. 방사선 종사자의 4년간(2012년~2015년) 누적선량에 따른 검사항목별 평균차이에서 5.0 mSv 초과 종사자가 백혈구 평균값에서 대조군 및 5.0 mSv 이하 피폭군에 비하여 낮은 값을 나타내었고, 적혈구($4.61{\pm}0.53$), 적혈구용적률($41.51{\pm}4.07$) 및 호산구($1.74{\pm}1.14$)는 대조군의 적혈구($4.91{\pm}0.38$), 적혈구용적률($43.97{\pm}3.40$), 호산구($2.92{\pm}1.39$)와 저선량 피폭자의 검사결과에 비하여 유의하게 낮은 값을 나타내었다. 0.5~1.0 mSv 피폭 종사자의 혈색소($13.93{\pm}1.75$)가 대조군($14.90{\pm}1.29$) 및 타 피폭자에 비하여 유의하게 낮은 값을 나타내었다.

• 대한방사선기술학회지:방사선기술과학
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• 제46권6호
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• pp.519-526
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• 2023

This study was intended to evaluate the shielding rate of radiation shields manufactured using 3D printers that have recently been used in various fields by comparing them with existing shields made of lead, and to find out their applicability through experiments. A 3D printer shield made of tungsten filament 1 mm, 2 mm, 4 mm shield, RNS-TX (nanotungsten) 1.1 mm, lead 0.2 mmPb, and 1mmPb were exposed to ^99mTc, ¹⁸F, and ²⁰¹TI for 15, 30, 45 minutes, and 60 minutes after measuring cumulative dose three times. Based on this, the shielding rate of each shield was calculated based on the dose in the absence of the shield. In addition, ^99mTc, ¹⁸F, and ²⁰¹TI were located 100 cm away from the phantom in which the OSLD nano Dot device was inserted, and if there was no shield for 60 minutes, the dose of thyroid was measured using 1.0 mm of lead shield, 1.1 mm of RNS-TX shield, and 2 mm of tungsten shield made by 3D printer. The use of shields during radiation shielding emitted from open radiation sources all resulted in a reduction in dose. The radiation dose emitted from the radionuclides under the experiment was all reduced when the shield was used. This study has been confirmed that tungsten is a material that can replace lead due to its excellent performance and efficiency as shield, and that it even shows the possibility of manufacturing a customized shield using 3D printer.

• Journal of Radiation Protection and Research
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• 제22권4호
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• pp.227-235
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• 1997

병원내 방사선 작업 종사자 51명(진단방사선과 18명, 치료방사선과 17명, 핵의학과 16명)에서 림프구의 염색체이상 빈도를 대조군 49명과 비교하여 저선량 만성피폭시 인체에 미치는 영향을 조사하였다. 종사자의 축적선량은 0.30-40.07 mSv 였으며 총축적선량 5 mSv 이하가 46%로 가장 많았다. 염색체 이상이 있는 세포수는 종사자군에서 1.275%로, 대조군에서의 0.677%에 비해 더 높았다(p<0.001). 염색분체형 이상은 종사자군이 약간 높은 경향은 있지만 통계적인 유의성은 없었으며, 염색체형 이상은 대조군 $0.344{\times}10^{-2}$/cell에 비해 종사자군이 $0.706{\times}10^{-2}$/cell로 2.1배 높았다(p<0.05). 이중 교환은 대조군 $0.083{\times}10^{-2}$/cell에 비해 종사자군 $0.245{\times}10^{-2}$/cell로 3.0배 높았다(p<0.05). 총축적선량, 최근 5년 및 최근 2년간의 선량은 염색체이상과 선량-반응 관계가 없었으나, 최근 1년간 피폭선량과 염색체형 교환 빈도사이에 유의한 상관관계가 있었다(p<0.05). 근무년수와 염색체 이상빈도와 선량-반응관계는 없었으며, 각 작업부서 별 염색체이상 빈도 및 대조군과의 비교시, 염색체형 교환이 핵의학과 $0.313{\times}10^{-2}$/cell로 가장 높았으며 (p<0.05), 치료방사선과 근무자 $0.265{\times}10^{-2}$/cell (p=0.0622), 진단방사선과 근무자 $0.167{\times}10^{-2}$/cell (p=0.1107)순이었다. 색체이상이 유발될 수 있음을 확인하였으며, 따라서 림프구 염색체이상은 매우 낮은 양의 방사선 피폭에 의하여도 발생함을 알 수 있었다.

• 한국방사선학회논문지
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• 제8권2호
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• pp.81-88
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• 2014

진단영상의학에서 일반영상촬영의 경우 각각의 부위를 연속(series)촬영으로 검사하는 경우가 대부분이다. 그러나 환자선량권고량(DRL)의 경우 각 부위의 전후(AP)방향과 측면(lateral)자세의 촬영 측정값만이 설정되어있는 것이 현실이다. 병원에서는 환자의 연속 촬영에 의해 누적 선량이 발생되며, 이는 환자선량권고량(DRL)과 누적된 피폭선량을 비교할 수 없거나, 과소평가할 수 있다. 본 연구에서 각 부위별 연속촬영의 누적선량을 측정한 결과, 조사야에 포함된 경우 입사표면선량(ESD)을 유효선량으로 변환하면 공중의 선량한도(Individual dose)의 최대 38.06%에서 최소 0.23%까지 측정되었다. 그리고 조사야에 포함되지 않은 각 부위의 입사표면선량(ESD)을 유효선량(Effective dose)으로 변환한 경우 공중의 선량한도(Individual dose)의 최대 5%에서 최소 0.04%까지 측정되었다. 연구결과 각 부위별 연속촬영에서 입사표면선량(ESD)이 많이 증가하는 것을 알 수 있다. 따라서 병원에서는 환자선량권고량(DRL)을 구체적으로 설정할 필요가 있으며, 불필요한 검사를 줄이기 위해 환자 촬영 order의 세분화가 필요하다고 판단된다. 또한, 여러 부위의 검사에서는 정확한 조사야의 필요성이 강조된다.

• Journal of Preventive Medicine and Public Health
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• 제31권4호
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• pp.616-627
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• 1998

In order to evaluate the cytogenetic hazard among hospital workers potentially exposed to low dose of radiation, the analysis of chromosome aberrations(CA) and sister chromatid exchanges(SCE) in lymphocytes were performed in 79 hospital workers and 79 non-exposed workers. The mean frequency of chromosomal exchange and deletion(respectively, $0.20\times10^{-2}/cell\;and\;0.39\times10^{-2}/cell$) in the exposed group were significantly higher than those$(0.07\times10^{-2}/cell\;and\;0.23\times10^{-2}/cell)$ in control group. The frequency of sister chromatid exchanges was 5.04/cell in the control vs. 6.57/cell in the exposed group. There were also significant differences in the mean frequencies of CA and SCE adjusted for age, sex, smoking, drinking between two groups. There were no evidence of significant increase of CA and SCE according to the department or duration of employment. But the frequency of cells having chromosome aberration was significantly higher in the exposed group than in the control group related to duration of employment. There was no dose-effect relationship between the cumulative doses and the frequency of CA and SCE. But in the case of last 1 yr cumulative dose, there were evidence of significant dose-dependant increase of chromosome type CA and percentage of cells with aberration. The result suggest that there is cytogenetic hazard in risk group like hospital workers handling low dose radiation. And the analysis CA and SCE are useful biological indicators for the exposure of low dose level of radiation.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1838-1854
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• 2023

This paper presents a hybrid algorithm to solve the multi-objective path planning (MOPP) problem for mobile robots in a static nuclear accident environment. The proposed algorithm mimics a real nuclear accident site by modeling the environment with a two-layer cost grid map based on geometric modeling and Monte Carlo calculations. The proposed algorithm consists of two steps. The first step optimizes a path by the hybridization of improved ant colony optimization algorithm-modified A^* (IACO-A^*) that minimizes path length, cumulative radiation dose and energy consumption. The second module is the high radiation dose rate avoidance strategy integrated with the IACO-A^* algorithm, which will work when the mobile robots sense the lethal radiation dose rate, avoiding radioactive sources with high dose levels. Simulations have been performed under environments of different complexity to evaluate the efficiency of the proposed algorithm, and the results show that IACO-A^* has better path quality than ACO and IACO. In addition, a study comparing the proposed IACO-A^* algorithm and recent path planning (PP) methods in three scenarios has been performed. The simulation results show that the proposed IACO-A^* IACO-A^* algorithm is obviously superior in terms of stability and minimization the total cost of MOPP.