• Nuclear Engineering and Technology
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• 제53권11호
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• pp.3824-3836
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• 2021

Workers' safety from radiological exposure in a 1 ton/day capacity spent resin treatment facility was evaluated according to the operating times and outflow rate due to process related leakages. The conservative annual dose based on the operating times of the workers exceeded the dose limit by at least 7.38E+01 mSv for close work. The realistic dose range was derived as 1.62E+01 mSv-6.60E+01 mSv. The conservative and realistic annual doses for remote workers were 1.33E+01 mSv and 3.00E+00 mSv respectively, which were less than the dose limit. The MWR was identified as the major contributor to worker exposure within the 1 h period required for removal of radioactive materials. The dose considering both internal and external exposures without APF was derived to be 1.92E+01 mSv for conservative evaluation and 4.00E+00 mSv for realistic evaluation. Furthermore, the dose with APF was derived as 7.27E-01 mSv for conservative evaluation and 1.51E-01 mSv for realistic evaluation. Considering the APF for leakage from all parts, the dose range was derived as 1.25E+00 mSv-2.03E+00 mSv for conservative evaluation and 2.61E-01 mSv-4.23E-01 mSv for realistic evaluation. Hence, it was confirmed that radiological safety was secured in the event of a leakage accident.

• 방사성폐기물학회지
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• 제22권1호
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• pp.45-54
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• 2024

Currently, off-site dose calculations for nuclear power plants are conducted using a computer program (K-DOSE 60). The program is developed based on the regulatory guidelines of the Korea Institute of Nuclear Safety (KINS), which is a domestic nuclear regulatory agency. In this study, a domestic application of the International Atomic Energy Agency (IAEA) TRS (Technical Reports Series)-472 methodology for ³H and ¹⁴C in liquid effluents was studied. The dose-evaluation methods adopted and the program configuration for dose evaluation are described based on ³H and ¹⁴C in the liquid-effluent-evaluation module of the computer program. The accuracy of the program is verified by comparing the program-calculated results with hand calculation values. Furthermore, a comparative evaluation with LADTAP II, which is a liquid-effluent-evaluation methodology developed by the U.S. NRC (Nuclear Regulatory Commission), is performed. The result confirms that the program-calculated results for the IAEA TRS-472 methodology are consistent with the hand calculation values. Meanwhile, the result of comparative evaluation with LADTAP II indicates different results depending on the methodology used.

• International Journal of Contents
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• 제8권2호
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• pp.52-59
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• 2012

This study uses digital imaging and communications in medicine (DICOM) files acquired after CT scan to obtain the absorbed dose distribution inside the body by using the patient's actual anatomical data; uses geometry and tracking (Geant)4 as a way to obtain the accurate absorbed dose distribution inside the body. This method is easier to establish the radioprotection plan through estimating the absorbed dose distribution inside the body compared to the evaluation of absorbed dose using thermo-luminescence dosimeter (TLD) with inferior reliability and accuracy because many variables act on result values with respect to the evaluation of the patient's absorbed dose distribution in diagnostic imaging and the evaluation of absorbed dose using phantom; can contribute to improving reliability accuracy and reproducibility; it makes significance in that it can implement the actual patient's absorbed dose distribution, not just mere estimation using mathematical phantom or humanoid phantom. When comparing the absorbed dose in polymethly methacrylate (PMMA) phantom measured in metal oxide semiconductor field effect transistor (MOSFET) dosimeter for verification of Geant4 and the result of Geant4 simulation, there was $0.46{\pm}4.69%$ ($15{\times}15cm^2$), and $-0.75{\pm}5.19%$ ($20{\times}20cm^2$) difference according to the depth. This study, through the simulation by means of Geant4, suggests a new way to calculate the actual dose of radiation exposure of patients through DICOM interface.

• 대한방사선치료학회지
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• 제30권1_2호
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• pp.83-95
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• 2018

목 적 : 폐암의 호흡동조방사선치료(Respiratory Gated Radiotherapy, RGRT)계획수립 후 표적 주변에 위치하고 있는 정상장기의 경우에는 움직임과 용적변화가 고려되지 않은 상태에서 선량평가가 이루어지는 경우가 많다. 본 연구에서는 적응형방사선치료(Adaptive Radiotherapy, ART)에서 많이 사용되는 변형영상정합(Deformable Image Registration, DIR)을 이용하여 호흡동조방사선치료 시 특정 위상에서의 정상장기의 움직임을 반영한 4차원-선량평가를 진행하였으며, 3차원 선량평가와의 차이를 연구하였다. 또한, 폐암의 치료계획평가 시 환자 호흡에 따른 정상장기의 움직임과 용적변화에 대한 분석 및 고려가 필요한 지 알아보고자 한다. 대상 및 방법 : 호흡동조방사선치료를 받은 폐암 환자 10명을 대상으로 하였다. Eclipse(Ver 13.6 Varian, USA)로 최고 위상 CT영상에 그려진 구조물을 모든 위상영상에 Propagation($Eclipse^{TM}$)이나 Segmentation Wizard($Eclipse^{TM}$)의 메뉴로 동일하게 설정하였으며, Center-to-Center 방식으로 구조물의 움직임 및 용적을 분석하였다. 또한, 4차원 선량평가를 위해 VELOCITY 프로그램(VELOCITY Ver 4.0, Varian, USA)을 이용하여 각 위상의 영상과 선량분포를 최고 위상 CT영상에 변형하였으며, 선량을 합산하여 정상장기의 4차원 선량평가를 실시하고, 3차원 선량평가와 비교분석을 하였다. 또한, 4차원 선량분포의 검증을 위해 $QUASAR^{TM}$ Phantom(Modus Medical Devices)과 $GAFCHROMIC^{TM}$ EBT3 Film(Ashland, USA)을 사용하여 4차원 감마분석을 시행하였다. 결 과 : 들숨과 날숨 구간의 움직임은 우측 폐가 축 방향 $0.989{\pm}0.34cm$로 가장 컸으며, 척수가 측 방향 -0.001 cm로 가장 작았다. 30~70 % 구간의 움직임은 식도가 축 방향 $0.52{\pm}0.21cm$로 가장 컸으며, 척수가 전후방향 $0.013{\pm}0.01cm$로 가장 작았다. 용적은 우측 폐가 33.5 %로 가장 큰 변화율을 보였다. 3차원 선량평가와 4차원 선량평가에서의 PTV 선량균질지수(Conformity Index, CI) 값과 처방선량지수(Homogeneity Index, HI) 값의 차이는 각각 최대 0.076, 0.021, 최소 0.011, 0.0으로 평가되었다. 정상장기의 경우 4차원 선량평가에서 0.0045~2.76 % 차이를 보였다. 모든 환자의 4차원 감마통과율은 평균 $98.1{\pm}0.42%$로 확인되었고, 모두 기준 95 %를 통과하였다. 결 론 : 모든 환자의 PTV 선량균질지수 값은 4차원 선량평가 시 더 유의한 값임을 확인할 수 있었으며, 처방 선량지수는 두 선량평가에서 차이를 보이지 않았다. 호흡에 의한 움직임이 고려된 4차원 선량분포에서 PTV 경계부분이 채워져 3차원 선량분포에서보다 선량이 더욱 균질한 것을 확인할 수 있었다. 정상장기의 4차원 선량평가에서 0.004~2.76 % 차이가 있었으며, 척수를 제외한 모든 정상장기에서 두 평가방법의 차이유의를 확인할 수 있었다. 정상장기의 3차원 선량평가 시 과소평가가 이루어 질 수 있다는 사실을 본 연구를 통해 알 수 있었으며, 호흡에 의한 정상장기의 선량변화가 예상되는 경우 변형영상정합을 이용한 4차원 선량평가를 고려할 수 있을 것이다. 변형영상정합을 이용한 4차원 선량평가는 환자의 호흡에 의한 정상장기의 움직임과 용적 변화를 반영하는 조금 더 현실적인 선량평가방법이 될 것이라고 사료된다.

• 방사선산업학회지
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• 제17권4호
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• pp.509-518
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• 2023

The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

• 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.

• 대한방사선기술학회지:방사선기술과학
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• 제43권6호
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• pp.431-441
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• 2020

The purpose of this study was to construct a model of MVCT(Megavoltage Computed Tomography) dose calculation by using Dosimetry Check™, a program that radiation treatment dose verification, and establish a protocol that can be accumulated to the radiation treatment dose distribution. We acquired sinogram of MVCT after air scan in Fine, Normal, Coarse mode. Dosimetry Check™(DC) program can analyze only DICOM(Digital Imaging Communications in Medicine) format, however acquired sinogram is dat format. Thus, we made MVCT RC-DICOM format by using acquired sinogram. In addition, we made MVCT RP-DICOM by using principle of generating MLC(Multi-leaf Collimator) control points at half location of pitch in treatment RP-DICOM. The MVCT imaging dose in fine mode was measured by using ionization chamber, and normalized to the MVCT dose calculation model, the MVCT imaging dose of Normal, Coarse mode was calculated by using DC program. As a results, 2.08 cGy was measured by using ionization chamber in Fine mode and normalized based on the measured dose in DC program. After normalization, the result of MVCT dose calculation in Normal, Coarse mode, each mode was calculated 0.957, 0.621 cGy. Finally, the dose resulting from the process for acquisition of MVCT can be accumulated to the treatment dose distribution for dose evaluation. It is believed that this could be contribute clinically to a more realistic dose evaluation. From now on, it is considered that it will be able to provide more accurate and realistic dose information in radiation therapy planning evaluation by using Tomotherapy.

• 대한디지털의료영상학회논문지
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• 제16권2호
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• pp.9-14
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• 2014

Purpose: The purpose of this study has attempted to evaluate and compare the image evaluation and exposure dose by respectively applying Filtered Back Projection(FBP), the existing test method, and Adaptive Statistical Iterative Reconstruction(ASIR) with different values of tube voltage during the Low Dose Computed Tomography(LDCT). Materials and Methods: With the image reconstruction method as basis, Chest Phantom was utilized with the FBP and ASIR set at 10%, 20% respectively, and the change of Tube Voltage (100kVp, 120kVp). For image evaluation, Back ground noise, Signal to Noise ratio(SNR) and Contrast to Noise ratio(CNR) were measured, and, for dose evaluation, CTDIvol and DLP were measured respectively. The statistical analysis was tested with SPSS(ver. 22.0), followed by ANOVA Test conducted after normality test and homogeneity test. (p<0.05). Results: In terms of image evaluation, there was no outstanding difference in Ascending Aorta(AA) SNR and Infraspinatus Muscle(IM) SNR with the different values of ASIR application(p<0.05), but a significant difference with the different amount of tube voltage(p>0.05). Also, there wasn't noticeable change in CNR with ASIR and different amount of Tube Voltage (p<0.05). However, in terms of dose evaluation, CTDIvol and DLP showed contrasting results(p<0.05). In terms of CTDIvol, the measured values with the same tube voltage of 120kVp were 2.6mGy with No-ASIR and 2.17mGy with 20%-ASIR respectively, decreased by 0.43mGy, and the values with 100kVp were 1.61mGy with No-ASIR and 1.34mGy with 20%-ASIR, decreased by 0.27mGy. In terms of DLP, the measured values with 120kVp were $103.21mGy{\cdot}cm$ with No-ASIR and $85.94mGy{\cdot}cm$ with 20%-ASIR, decreased by $17.27mGy{\cdot}cm$(about 16.7%), and the values with 100kVp were $63.84mGy{\cdot}cm$ with No-ASIR and $53.25mGy{\cdot}cm$ with 20%-ASIR, a decrease by $10.62mGy{\cdot}cm$(about 16.7%). Conclusion: At lower tube voltage, the rate of dose significantly decreased, but the negative effects on image evaluation was shown due to the increase of noise. For the future, through the result of the experiment, it is considered that the method above would be recommended for follow-up patients or those who get health checkup as long as there is no interference on the process of diagnosis due to the characteristics of Low Dose examination.

• 농업과학연구
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• 제43권1호
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• pp.109-115
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• 2016

Silk has had a reputation as a luxurious and sensuous fabric but it is not popular due to the expensive price and poor durability. To develop the silk materials that apply the various industries, the artificially synthesized gene can be introduced into the silkworm and expressed in the silk gland. Transgenic silkworms for the mass production of green fluorescent silks are generated using a fibroin H-chain expression system. For commercial use, safety assessment of the transgenic silkworms is essential. The purpose of this study was to examine the potential acute oral toxicity of EGFP protein expressed in genetically modified (GM) fluorescence silkworm and to obtain the approximative lethal dose in the male and female at 6-weeks ICR mice. EGFP protein was fed at a dose of 2,000 mg/kg body weight in five male or five female mice. Mortalities, clinical findings and body weight changes were monitored for 1, 3, 7, 14 days after dosing. At the end of 14 day observation period, all mice were sacrificed, and the postmortem necropsy were performed. The test group was not observed death case. Also the effect was not admitted by test substance administration in common symptoms, the body weight and postmortem. The results of single-dose oral toxicity test showed that approximative lethal dose of EGFP protein expressed in fluorescence silkworm was considered to exceed the 2,000 mg/kg body weight in both sexes.

• 방사선산업학회지
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• 제17권4호
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• pp.437-442
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• 2023

This study conducted a comparative analysis of dose evaluations for ingestion of animal products based on data from nuclear power plants in the Republic of Korea, using methodologies from the Republic of Korea, 'IAEA TRS-472', and 'CSA N288.1:14'. The research focused on tritium, the most significant constituent among the gaseous and liquid radioactive emissions. The combined evaluation of tritium, in the form of tritiated water (HTO) and organically bound tritium (OBT), yielded results of 1.143 μSv y^-1 for the Republic of Korea, 0.965μSv y^-1 for 'TRS-472', and 0.886μSv y^-1 for 'N288.1:14'. Despite the Republic of Korea's guidelines not considering OBT, the evaluation results for the Republic of Korea were higher compared to other methodologies. This discrepancy was attributed to the unique approach of not considering the moisture content per individual in the calculations of plant and feed concentration in the Republic of Korea and the simultaneous consideration of specific-activity model and transfer model. The study highlights the necessity of developing dose evaluation models tailored to regional characteristics and underscores the importance of including OBT in these evaluations.