• Journal of Radiation Protection and Research
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• 제48권1호
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• pp.44-51
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• 2023

Background: Aptamers are currently being used in various fields including medical treatments due to their characteristics of selectively binding to specific molecules. Due to their special characteristics, the aptamers are expected to be used to remove radionuclides from a large amount of liquid radioactive waste generated during the decommissioning of nuclear power plants. The radiological effects on the aptamers should be evaluated to ensure their integrity for the application of a radionuclide removal technique. Materials and Methods: In this study, Monte Carlo N-Particle transport code version 6 (MCNP6) and Monte Carlo damage simulation (MCDS) codes were employed to evaluate the radiological effects on the aptamers. MCNP6 was used to evaluate the secondary electron spectrum and the absorbed dose in a medium. MCDS was used to calculate the DNA damage by using the secondary electron spectrum and the absorbed dose. Binding experiments were conducted to indirectly verify the results derived by MCNP6 and MCDS calculations. Results and Discussion: Damage yields of about 5.00×10^-4 were calculated for 100 bp aptamer due to the radiation dose of 1 Gy. In experiments with radioactive materials, the results that the removal rate of the radioactive ⁶⁰Co by the aptamer is the same with the non-radioactive ⁵⁹Co prove the accuracy of the previous DNA damage calculation. Conclusion: The evaluation results suggest that only very small fraction of significant number of the aptamers will be damaged by the radioactive materials in the liquid radioactive waste.

• 한국의학물리학회지:의학물리
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• 제33권4호
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• pp.150-157
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• 2022

Purpose: Elekta synergy^® was commissioned in the Seoul National University Veterinary Medical Teaching Hospital. Recently, Chung-Ang University Gwang Myeong Hospital commissioned Elekta Versa HD^TM. The beam characteristics of both machines are similar because of the same Agility^TM MLC Model. We compared measured beam data calculated using the Elekta treatment planning system, Monaco^®, for each institute. Methods: Beam of the commissioning Elekta linear accelerator were measured in two independent institutes. After installing the beam model based on the measured beam data into the Monaco^®, Monte Carlo (MC) simulation data were generated, mimicking the beam data in a virtual water phantom. Measured beam data were compared with the calculated data, and their similarity was quantitatively evaluated by the gamma analysis. Results: We compared the percent depth dose (PDD) and off-axis profiles of 6 MV photon and 6 MeV electron beams with MC calculation. With a 3%/3 mm gamma criterion, the photon PDD and profiles showed 100% gamma passing rates except for one inplane profile at 10 cm depth from VMTH. Gamma analysis of the measured photon beam off-axis profiles between the two institutes showed 100% agreement. The electron beams also indicated 100% agreement in PDD distributions. However, the gamma passing rates of the off-axis profiles were 91%-100% with a 3%/3 mm gamma criterion. Conclusions: The beam and their comparison with MC calculation for each institute showed good performance. Although the measuring tools were orthogonal, no significant difference was found.

• 대한방사선치료학회지
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• 제14권1호
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• pp.175-186
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• 2002

The purpose of this study is directly measure and evaluate about absorbed dose change according to nominal energy and electron cone or medical accelerator on isodose curve, percentage depth dose, contaminated X-ray, inhomogeneous tissue, oblique surface and irradiation on intracavitary that electron beam with high energy distributed in tissue, and it settled standard data of hish energy electron beam treatment, and offer to exactly data for new dote distribution modeling study based on experimental resuls and theory. Electron beam with hish energy of $6{\sim}20$ MeV is used that generated from medical linear accelerator (Clinac 2100C/D, Varian) for the experiment, andwater phantom and Farmer chamber md Markus chamber und for absorbe d dose measurement of electron beam, and standard absorbed dose is calculated by standard measurements of International Atomic Energy Agency(IAEA) TRS 277. Dose analyzer (700i dose distribution analyzer, Wellhofer), film (X-OmatV, Kodak), external cone, intracavitary cone, cork, animal compact bone and air were used for don distribution measurement. As the results of absorbed dose ratio increased while irradiation field was increased, it appeared maximum at some irradiation field size and decreased though irradiation field size was more increased, and it decreased greatly while energy of electron beam was increased, and scattered dose on wall of electron cone was the cause. In percentage depth dose curve of electron beam, Effective depth dose(R80) for nominal energy of 6, 9, 12, 16 and 20 MeV are 1.85, 2.93, 4.07, 5.37 and 6.53 cm respectively, which seems to be one third of electron beam energy (MeV). Contaminated X-ray was generated from interaction between electron beam with high energy and material, and it was about $0.3{\sim}2.3\%$ of maximum dose and increased with increasing energy. Change of depth dose ratio of electron beam was compared with theory by Monte Carlo simulation, and calculation and measured value by Pencil beam model reciprocally, and percentage depth dose and measured value by Pencil beam were agreed almost, however, there were a little lack on build up area and error increased in pendulum and multi treatment since there was no contaminated X-ray part. Percentage depth dose calculated by Monte Carlo simulation appeared to be less from all part except maximum dose area from the curve. The change of percentage depth dose by inhomogeneous tissue, maximum range after penetration the 1 cm bone was moved 1 cm toward to surface then polystyrene phantom. In case of 1 cm and 2 cm cork, it was moved 0.5 cm and 1 cm toward to depth, respectively. In case of air, practical range was extended toward depth without energy loss. Irradiation on intracavitary is using straight and beveled type cones of 2.5, 3.0, 3.5 $cm{\phi}$, and maximum and effective $80\%$ dose depth increases while electron beam energy and size of electron cone increase. In case of contaminated X-ray, as the energy increase, straight type cones were more highly appeared then beveled type. The output factor of intracavitary small field electron cone was $15{\sim}86\%$ of standard external electron cone($15{\times}15cm^2$) and straight type was slightly higher then beveled type.

• Journal of Radiation Protection and Research
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• 제32권1호
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• pp.15-20
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• 2007

An empirical formula fur the neutron dose equivalent at the maze entrance of medical accelerator treatment rooms was derived on the basis of a Monte Carlo simulation. The simulated neutron dose equivalents around the Varian medical accelerator by the MCNPX code were employed. Two cases of target rotational planes were considered: parallel and perpendicular to maze walls. Most of the maximum neutron dose equivalents at the doorway were found when the target rotational planes were parallel to maze walls and the beams were directed to the inner maze entrances. The neutron dose equivalents at the outer maze entrances were calculated for about 698 medical accelerator facilities which were generated from the geometry configurations of running treatment rooms, based on such gantry rotation that produces the maximum neutron dose at the doorway. The results calculated with the empirical formula in this study were compared with those calculated by the Kersey method for 7 operating facilities. It was found that the maximum disagreement between the calculation of this study and that of the Kersey method was a factor of 8.54 with the value calculated by the Kersey method exceeding that of this study. It was concluded that the kersey method estimated the neutron dose equivalent at the doorway computed by MCNPX more conservatively than this study technique.

• Journal of Astronomy and Space Sciences
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• 제19권2호
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• pp.151-162
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• 2002

인공위성에서의 우주방사선 차폐계산을 위한 근사계산 방법으로 sectoring method를 적용하는 방법과 chord-length 분포를 이용하는 방법을 상세 계산 결과와 비교하였다. 저 궤도 위성인 우리별 1호를 대상으로 양성자의 차폐계산을 수행하였다. 이때 방사선환경은 AP-8 model을 이용하여 구한 SAA(South Atlantic Anomaly)지역으로 가정하였다. Sectoring method와 chord-length 분포를 이용하는 방법은 양성자가 물질내에서 직진한다는 기본적인 가정을 사용하므로 3차원 상세계산 결과와 비교하여 어느 정도의 오차를 갖는다. 그러나 우리별 1호를 대상으로 수행된 계산 결과에서 두 계측기 위치에서의 피폭량 예측은 2가지 근사모델이 모두 상세계산 결과와 근사하게 일치하였다.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.149-154
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• 2001

Calculational models to evaluate radiation doses resulting from the medical use of high energy beta-ray sources are presented. The radioactive sources considered are Sr-90/Y-90 used as ophthalmic applicator, Re-188 used for treating restenosis of coronary artery, and Ho-166 used for treating hepatic tumors. Typical therapeutic situations which might induce relatively high radiation doses the medical person involved were considered to compute by using MCNP-4C Monte Carlo code the radiation doses. The calculation results suggest that for all of the cases considered, the evaluated radiation doses are negligible compared to the dose limits. It is also found that the effect of Bremsstrahlung radiations on the total dose is insignificant, and hence the conventional lead gown is also effective in shielding beta-rays.

• Journal of Radiation Protection and Research
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• 제16권2호
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• pp.67-74
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• 1991

육상 섭취 경로에 따른 내부 피폭선량 계산 모델 KFOOD의 파라메터 불착실성 및 민감도를 몬테칼로법을 사용하여 수치 분석하였다. 쌀을 통한 섭취 경로의 경우 KFOOD 코드에 의한 예측치는 아주 보수적인 값을 나타내었다 모델에서 민감도가 큰 입력변수는 방사능의 침적속도와 식물전이제수였다.

• Radiation Oncology Journal
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• 제13권3호
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• pp.285-289
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• 1995

목적 : 6 MeV의 전자선에 대하여 Monte-Carlo기법을 이용한 모의계산(simulation)과 측정을 함으로써 측정값과 계산값을 서로 비교하고, 이러한 모의계산이 측정을 대신할 수 있을 만큼의 정확도가 있는지를 확인하고자 하였다. 방법 : 선형가속기에서 출력되는 전자선의 심부량 백분율(percent depth dose)을 물팬톰에서 반도체 검출기를 이용하여 조사야 $50{\times}50,\;100{\times}100,\;150{\times}150,\;200{\times}200\;mm^2$에 대하여 측정하였다. 전자선에 대한 선량을 결정하기 위한 모의계산은 EGS4 프로그램을 사용하였다. 결과 : 측정값과 계산값은 유사한 형태로 나타났는데 $100{\times}100\;mm^2$ 조사야 에서 선축상최대선량은 측정값과 계산값이 각각 14mm 와 15mm, 표면선량율은 각각 $76.94\%$ 와 $65.52\%$였다. 모의계산에서 표면선량율의 조사야에 따른 변화는 $64.43\%-66.99\%$이고 선축상최대선량은 15mm-18mm 였다. 결론 : 모의계산을 한 결과, 계산값이 측정값과 비교적 잘 일치한다는 것을 알았다. 표면선량율의 차이만을 제거하고 결과를 살펴보면 선축상 최대치등 방사선 치료에 주로 이용되는 부츤의 선량율에서는 모의계산이 측정을 대신할 수 있을 만큼의 정확도가 있다는 것을 확인하였다.

• 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.

• 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.