• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.324-324
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• 1998

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.349-350
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• 2019

• 대한방사선기술학회지:방사선기술과학
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• 제22권1호
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• pp.13-20
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• 1999

This study is to calculate the exposed radiation dose using Bit method, NDD calculation method and monogram method without dosimeter. In addition, we can calculate the radiation dose from x-ray film density as a film badge. The authors examined the entrance skin dose from $2{\sim}3$ intercostal chest x-ray film density. We also studied the relationship between film density and equivalent dose in the each screen film system under the different radiation quality and the poor geometry condition of grid ratio. As results, we established the deductive method to define the entrance skindose from chest x-ray film density. The error range was found in the range $-13%{\sim}+l7%$ for between deductive entrance skindose and the $2{\sim}3$ intercostal chest x-ray film density to actual detective radiation dose with dosimeter.

• 한국의학물리학회지:의학물리
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• 제15권1호
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• pp.39-44
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• 2004

본 연구에서는 깊이선량률의 측정값과 단일에너지 계산값들로부터 치료용 전자선에 대한 에너지분포를 계산하였다. 최소제곱법에 기초한 수치연산을 이용하여 측정과 환산 깊이선량률의 차이가 최소가 되는 에너지분포를 결정하였다. 본 방법은 임상에 이용되는 명목에너지 6, 9, 12, 그리고 15 MeV 전자선에 대하여 적용되었다. 본 연구에서는 측정값과의 비교를 위하여 결정된 에너지분포를 입력자료로 이용한 깊이선량률의 몬테칼로 계산을 수행하였다. 계산된 깊이선량률을 측정값과 비교할 때, 모든 전자선에 대하여 표면에서 R$_{80}$ 깊이까지 측정값과 $\pm$3% 미만, 비정 근처까지 $\pm$4% 미만의 상대오차를 보였다. 본 연구는 입사 전자선의 에너지분포를 결정하기 위한 실용적 방법으로 응용될 수 있다.

• 한국방사선학회논문지
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• 제10권4호
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• pp.271-278
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• 2016

본 연구는 유방암의 근접치료 시 수학적 모의피폭체를 이용하여 유방 및 인접장기의 선량을 평가하고자 하였다. 좌측 유방과 우측 유방을 선원으로 설정하여 $^{192}Ir$과 $^{103}Pd$ 핵종에 대한 흡수선량을 분석하였다. 그 결과 선원 장기에 대한 선량은 $^{192}Ir$이 $^{103}Pd$에 비해 높은 흡수선량을 보였으며, 반대측 유방의 선량도 $^{192}Ir$이 높게 나타났다. 또한 유방암의 근접치료 시 특히 유의해야 할 인접장기는 폐, 간, 심장, 반대측 유방으로 평가되었다.

• Journal of Radiation Protection and Research
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• 제37권3호
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• pp.146-148
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• 2012

The use of GEANT4 simulation toolkit has increased in the radiation medical field for the design of treatment system and the calibration or validation of treatment plans. Moreover, it is used especially on calculating dose simulation using medical data for radiation therapy. However, using internal visualization tool of GEANT4 detector constructions on expressing dose result has deficiencies because it cannot display isodose line. No one has attempted to use this code to a real patient's data. Therefore, to complement this problem, using the result of gMocren that is a three-dimensional volume-visualizing tool, we tried to display a simulated dose distribution and isodose line on medical image. In addition, we have compared cross-validation on the result of gMocren and GEANT4 simulation with commercial radiation treatment planning system. We have extracted the analyzed data of dose distribution, using real patient's medical image data with a program based on Monte Carlo simulation and visualization tool for radiation isodose mapping.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1176-1179
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• 2019

Measurements of activity concentrations of radionuclides in atmospheric releases were performed in 2017-2018 at vent stacks of seven Russian nuclear power plants. The selected instruments and research methods, with detection limits significantly lower than the existing detection limit of Russian NPPs routine control, allowed to reliably determine up to 26 radionuclides. Analysis of experimental data allows to determine the list of radionuclides for calculation the effective dose rates to public and the permissible annual discharge levels for each Russian NPP. Radiocarbon is determined as major contributor for the dose from the atmospheric releases of LWGR reactors - up to 98% for EGP-6 and RBMK-1000 (Smolensk NPP) reactors. For PWR reactors (VVER) radionuclides contribution to the annual dose from atmospheric releases is more complicated, but, in general, dose is formed by tritium, $^{14}C$ and noble gases. The special monitoring results with ranking of measured radionuclides according to their contribution to the effective dose makes it possible to optimize the list of controlled radionuclides in airborne releases of Russian NPPs from 94 to 8-16 for different NPPs.

• 한국환경과학회지
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• 제31권3호
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• pp.227-235
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• 2022

In this study, a biodegradation model of based on molecular cellulose was established. It is a mathematical, kinetic model, assuming that two major enzymes randomly break glycosidic bonds of cellulose molecules, and calculates the number of molecules by applying the corresponding probability and degradation reaction coefficients. Model calculations considered enzyme dose, cellulose chain length, and reaction rate constant ratio. Degradation increased almost by two folds with increase of temperature (5℃→25℃). The change of degradation was not significant over the higher temperatures. As temperature increased, the degradation rate of the molecules increased along with higher production of shorter chain molecules. As the reaction rates of the two enzymes were comparative the degree of degradation for any combinations of enzyme application was not affected much. Enzyme dose was also tested through experiment. While enzyme dose ranged from 1 mg/L to 10 mg/L, the gap between real data and model calculations was trivial. However, at higher dose of those enzymes (>15 mg/L), the experimental result showed the lower concentrations of reductive sugar than the corresponding model calculation did. We determined that the optimal enzyme dose for maximum generation of reductive sugar was 10 mg/L.

• 대한방사선치료학회지
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• 제18권2호
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• pp.75-80
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• 2006

목 적: 방사선치료에 있어 종양조직이나 정상조직의 정확한 선량계산은 치료의 성패를 좌우하는 가장 큰 요인이다. 이로 인해 방사선치료계획은 컴퓨터 단층 영상의 재구성을 통한 불균질 조직에 선흡수계수를 밀도로 변환하여 CT 번호에 의한 선량 보정이 유효하게 이루어지고 있다. 대상 및 방법: 이에 본 연구는 불균질 조직등가 팬톰을 제작하여 현재 사용 중인 방사선 치료 계획시스템을 이용한 CT 번호의 측정과 질량밀도를 계산하여 물을 기준으로 상대값을 구하였다. 또한 실제 방사선 조사 시 측정된 선량(nC)과 CT영상을 이용한 치료계획 시 선량(PDD)을 상대적으로 비교함으로써 실제 CT 번호를 이용한 불균질 조직의 보정에 대한 유용성과 정확성을 평가하고자 한다. 결 과: 측정결과 CT 번호를 이용하여 계산된 조직등가물질의 질량밀도와 실제 질량밀도는 $0.005{\sim}0.069g/cm^3$의 차이를 보였으며, 방사선 치료계획 시 심부선량(PDD)과 방사선 치료 장치로 조사하여 측정된 선량의 상대오차는 $-2.8{\sim}+1.06%$로 3% 이내의 유효범위이내의 결과를 얻었다. 결 론: 본 실험은 CT 영상을 이용한 불균질 조직의 보정에 대한 유용성을 확인할 수 있었고, 방사선 치료 계획 장치의 정도 관리(Quality Assurance; QA)의 기본 틀을 제공할 수 있을 것으로 사료된다.

• Journal of Radiation Protection and Research
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• 제45권1호
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• pp.45-52
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• 2020

Background: Recently, the International Commission on Radiological Protection (ICRP) lowered the dose limit for the eye lens from 150 mSv to 20 mSv, highlighting the importance of accurate lens dose estimation. The ICRP reference computational phantoms used for lens dose calculation are mostly based on the data of Caucasian population, and thus might be inappropriate for Korean population. Materials and Methods: In the present study, a detailed Korean eye model was constructed by determining nine ocular dimensions using the data of Korean subjects. The developed eye model was then incorporated into the adult male and female mesh-type reference Korean phantoms (MRKPs), which were then used to calculate lens doses for photons and electrons in idealized irradiation geometries. The calculated lens doses were finally compared with those calculated with the ICRP mesh-type reference computational phantoms (MRCPs) to observe the effect of ethnic difference on lens dose. Results and Discussion: The lens doses calculated with the MRKPs and the MRCPs were not much different for photons for the entire energy range considered in the present study. For electrons, the differences were generally small, but exceptionally large differences were found at a specific energy range (0.5-1 MeV), the maximum differences being about 10 times at 0.6 MeV in the anteroposterior geometry; the differences are mainly due to the difference in the depth of the lens between the MRCPs and the MRKPs. Conclusion: The MRCPs are generally considered acceptable for lens dose calculations for Korean population, except for the electrons at the energy range of 0.5-1 MeV for which it is suggested to use the MRKPs incorporating the Korean eye model developed in the present study.