• 방사선산업학회지
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• 제17권2호
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• pp.151-160
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• 2023

The International Atomic Energy Agency (IAEA) proposes 11 industries that handle Naturally Occurring Radioactive Material (NORM) that are considered to need management. A water treatment facility is one of the above industries that takes in groundwater and produces drinking water through a water treatment process. Groundwater can accumulate natural radionuclides such as uranium and thorium in raw water by contacting rocks or soil containing natural radionuclides. Therefore, there is a possibility that workers in water treatment facilities will be exposed due to the accumulation of natural radionuclides in the water treatment process. The goal of this study is to evaluate the external radiation dose according to the working type of workers in water treatment facilities. In order to achieve the above goal, the study was conducted by dividing it into 1) analysis of the exposure environment, 2) measurement of the external radiation dose rate 3) evaluation of the external radiation dose. In the stage of analyzing the exposure environment, major processes that are expected to occur significantly were derived. In the measurement stage of the external radiation dose rate, a map of the external radiation dose rate was prepared by measuring the spatial radiation dose rate in major processes. Through this, detailed measurement points were selected considering the movement of workers. In the external radiation dose evaluation stage, the external radiation dose was evaluated based on the previously derived external radiation dose rate and working time. As a result of measuring the external radiation dose rate at the detailed points of water treatment facilities A to C, it was 1.90×10^-1 to 3.75×10⁰ μSv h^-1, and the external radiation dose was analyzed as 3.27×10^-3 to 9.85×10^-2 mSv y^-1. The maximum external radiation dose appeared during the disinfection and cleaning of activated carbon at facility B, and it is judged that natural radionuclides were concentrated in activated carbon. It was found that the external radiation dose of workers in the water treatment facility was less than 1mSv y^-1, which is about 10% of the dose limit for the public. As a result of this study, it was found that the radiological effect of external radiation dose of domestic water treatment facility workers was insignificant. The results are expected to contribute as background data to present optimized safety management measures for domestic NORM industries in the future.

• 대한방사선기술학회지:방사선기술과학
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• 제37권1호
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• pp.7-14
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• 2014

인공방사선 사용이 가장 많은 진단방사선 분야의 피폭선량 저감에 착안하여 X-선 조사의 1차적 사용자인 방사선사의 기술적인 연구에 의해 피폭선량을 감소시키고자 흉부팬텀인 DUKE phantom을 이용하여 X-선 발생장치에서 부가여과를 적용해 피폭선량의 감소 효과를 알아보고 PC-Based Monte Carlo Program(PCXMC)을 이용하여 환자가 받는 유효선량 및 장기선량에 대해 알아보기 위해 본 연구를 시행하였다. 본 실험에서는 설정된 조건을 사용하여 알루미늄만을 이용한 단일여과와 구리와 알루미늄을 이용한 복합여과를 적용하여 DUKE Phantom에서 나타난 구리 원반(copper disc)의 개수를 측정하여 단일여과와 복합여 과의 조합에서 구리 원반의 개수가 같으면서 흡수선량이 가장 적은 부가여과의 조합을 찾고 PCXMC 2.0 프로그램을 이용하여 유효선량 및 장기선량을 산출하였다. 사용 관전류에 따라 다르지만 관전압 80 kVp, AP Projection 조건에서는 최소 약 30 % ~ 최대 약 84 %의 유효선량을 감소시킬 수 있었고 관전압 120 kVp, PA Projection 조건에서는 최소 약 41 % ~ 최대 약 71 %의 유효선량을 감소시킬 수 있었다. 장기선량은 각 장기마다 선량 감소율이 달랐으나 최소 30 % ~ 최대 100 %의 선량 감소율을 보였다. 본 연구를 통하여 같은 촬영 조건을 사용하더라도 부가여과를 통해 낮은 선량으로 영상의 품질 면에서 변화가 없었으며 DUKE Phantom과 PCXMC 2.0 프로그램을 이용한 장기선량과 유효선량에 대한 저감 효과를 산출하는 것에 적합하였음을 알 수 있었다.

• 한국의학물리학회지:의학물리
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• 제20권1호
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• pp.7-13
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• 2009

본 논문은 물 흡수선량 표준에 기반하여 근접치료 선원인 $^{192}Ir$을 교정하는 것에 대한 예비적 연구를 위한 것이다. 이온함을 사용하여 물흡수선량 표준에 기반하여 근접치료 선원을 교정하기 위해선, 빔 선질 교정인자인 $k_{Q,Q_0}$가 필요하다. 본 연구에선 일차 표준을 사용하여 지정된 거리에서의 흡수선량를 측정하는 데 있어서의 현실적인 어려움 때문에 몬테칼로 전산모사와 반실험적인 방법을 통하여 $k_{Q,Q_0}$를 결정하였다. 본 연구를 위해 PTW30013 이온함 5개를 선택하였다. 포괄적 $k^{gen}_{Q,Q_0}$ 값의 경우엔 이온함간 변화가 최대 4.0%에 이른 반면, 개별적 $k^{ind}_{Q,Q_0}$ 경우엔 이온함간 변화가 최대 0.5% 이내였다. 이 결과는 물 흡수선량에 기반하여 근접치료 선원인 $^{192}Ir$을 교정시에 이온함을 왜 개별적으로 교정해야 하는지, 개별적인 교정이 얼마나 중요한 지를 보여 준다. 가까운 장래에 공기커마 세기 대신에 사용자가 근접치료 선원을 고에너지 광자빔과 전자빔의 교정에서처럼 치료에서 관심있는 물리량인 물흡수선량의 관점에서 교정할 수 있기를 희망한다.

• 한국의학물리학회지:의학물리
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• 제16권4호
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• pp.161-165
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• 2005

CT 기종에 따라서 전자밀도에 대응하는 CT 수의 변화와 치료계획 시 선량계산에 미치는 영향을 분석하였다. 5종의 CT를 이용하여 전자밀도 교정 팬톰의 영상을 얻어 기종에 따른 CT 수의 변화를 알아보았다. 조직등가물질의 밀도에서 CT 수는 ${\pm}2\%$ 내의 차이를 보였으나 밀도가 큰 영역에서는 최대 $9.5\%$의 차이를 나타냈다. CT 수의 변화가 치료계획의 선량계산에 미치는 영향을 알아보기 위하여 환자의 흉부 영상을 이용하여 장기별로 선량의 차이를 분석한 결과 최대 $0.48\%$로 거의 차이를 보이지 않았다. 밀도가 큰 물질이 인체 내에 삽입되어 있을 경우를 가정하여 물팬톰에 CT 수가 2,000인 고밀도 물질을 삽입한 팬톰 영상을 치료계획장치에 그려 넣었다. 고밀도 물질 아래 20 cm 깊이에서 선량 계산을 비교한 결과 $2.1\%$의 차이를 보였다. 치료계획 단계에서 선량 불확도를 최소화하기 위해서는 사용되는 CT 기종에 따른 CT수와 전자밀도의 정확한 환산이 필요하며, 특히 한 기관에서 여러 종류의 CT를 이용하는 경우 각 CT 별로 전자밀도에 대응하는 CT 수를 입력하고 서로 구별하여 사용하여야한다. 또한 CT수의 재현성을 확인하기 위해 주기적인 점검이 요구된다.

• Journal of Korean Neurosurgical Society
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• 제42권4호
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• pp.286-292
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• 2007

Objective : Gamma Knife Stereotactic Radiosurgery (GK SRS) has become an important treatment modality for vestibular schwannomas. We evaluated the tumor control rate, patterns of tumor volume change and preservation of hearing following low-dose radiation for vestibular schwannomas in a homogeneous cohort group in which the mean marginal dose was 12 Gy. Methods : A total of 59 patients were enrolled in this study. All enrolled patients were followed-up for at least 5 years and the radiation dose was 11-13 Gy. Regular MRI, audiometry and clinical evaluations were done and tumor volumes were obtained from MRI using the OSIRIS program. Results : The tumor control rate was 97%. We were able to classify the patterns of change in tumor volume into three categories. Transient increases in tumor volume were detected in 29% of the patients and the maximum transient increase in tumor volume was identified at 6 to 30 months after GK SRS. The transient increases in tumor volume ranged from 121% to 188%. Hearing was preserved in 4 of the 12 patients who had serviceable hearing prior to treatment. There were no other complications associated with GK SRS. Conclusion : Low-dose GK SRS was an effective and safe mode of treatment for vestibular schwannomas in comparison to the previously used high-dose GK SRS. Transient increases in tumor volume can be identified during the follow-up period after low-dose GK SRS for vestibular schwannomas. Physicians should be aware that these increases are not always indicative of treatment failure and that close observation is required following treatments. Unfortunately, a satisfactory hearing preservation rate was not achieved by reducing the radiation dose. It is thought that hearing preservation is a more sophisticated problem and further research is required.

• Journal of Radiation Protection and Research
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• 제40권3호
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• pp.147-154
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• 2015

The scatter photons and photoneutrons from high energy photon beams (more than 10 MV) will increase the undesired dose to the patient and the staff working in linear accelerator room. This undesired dose which is found at out-of-field area can increase the probability of secondary malignancy. The purpose of this study is to determine the equivalent dose of scatter photons and neutrons generated by 3 different treatment techniques: 3D-conformal, intensity modulated radiation therapy (IMRT) and volumetric modulated arc therapy (VMAT). The measurement was performed using two types of the optically stimulation luminescence detectors (OSL and OSLN) in the Alderson Rando phantom that was irradiated by 3 different treatment techniques following the actual prostate cancer treatment plans. The scatter photon and neutron equivalent dose were compared among the 3 treatments techniques at the surface in the out-of-field area and the critical organs. Maximum equivalent dose of scatter photons and neutrons was found when using the IMRT technique. The scatter neutrons showed average equivalent doses of 0.26, 0.63 and $0.31mSv{\cdot}Gy^{-1}$ at abdominal surface region which was 20 cm from isocenter for 3D, IMRT and VMAT, respectively. The scattered photons equivalent doses were 6.94, 10.17 and $6.56mSv{\cdot}Gy^{-1}$ for 3D, IMRT and VMAT, respectively. For the 5 organ dose measurements, the scattered neutron and photon equivalent doses in out of field from the IMRT plan were highest. The result revealed that the scatter equivalent doses for neutron and photon were higher for IMRT. So the suitable treatment techniques should be selected to benefit the patient and the treatment room staff.

• 한국의학물리학회지:의학물리
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• 제16권1호
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• pp.39-46
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• 2005

m3 (BrainLAB Inc., Germany)를 이용한 두경부 IMRT의 정도관리에서 테이블과 갠트리의 위치에 따라 테이블에 의한 선량감쇠가 일어나 정확한 처방 선량을 측정할 수 없다. 이 문제를 해결하기 위해 두경부 종양의 세기변조방사선치료를 위해 Brain Lab사의 환자테이블 mount를 이용해 설치할 수 있는 원통형 두경부 팬톰을 제작하였다. 이를 이용하여 환자테이블에 의한 선량 감쇠를 측정하고 실제 임상에 적용함으로써 테이블에 의한 선량 감쇠로 인한 선량분포의 차이를 확인할 수 있었다. 측정결과 환자테이블에 의한 점 선량의 감쇠가 최대 약 35%가 났으며 실제 환자 치료계획에 대한 정도관리에서의 절대점 선량의 경우 5.4%의 선량차이를 나타냈다.

• Nuclear Engineering and Technology
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• 제48권2호
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• pp.525-532
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• 2016

High-energy linear accelerators are increasingly used in the medical field. However, the unwanted photo-neutrons can also be contributed to the dose delivered to the patients during their treatments. In this study, neutron fluxes were measured in a solid water phantom placed at the isocenter 1-m distance from the head of an18-MV linac using the foil activation method. The produced activities were measured with a calibrated well-type Ge detector. From the measured fluxes, the total neutron fluence was found to be $(1.17{\pm}0.06){\times}10^7n/cm^2$ per Gy at the phantom surface in a $20{\times}20cm^2$ X-ray field size. The maximum photo-neutron dose was measured to be $0.67{\pm}0.04$ mSv/Gy at $d_{max}=5cm$ depth in the phantom at isocenter. The present results are compared with those obtained for different field sizes of $10{\times}10cm^2$, $15{\times}15cm^2$, and $20{\times}20cm^2$ from 10-, 15-, and 18-MV linacs. Additionally, ambient neutron dose equivalents were determined at different locations in the room and they were found to be negligibly low. The results indicate that the photo-neutron dose at the patient position is not a negligible fraction of the therapeutic photon dose. Thus, there is a need for reduction of the contaminated neutron dose by taking some additional measures, for instance, neutron absorbing-protective materials might be used as aprons during the treatment.

• 한국의학물리학회지:의학물리
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• 제31권4호
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• pp.145-152
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• 2020

Purpose: In ionization-chamber dosimetry for high-dose-rate electron beams-above 20 mGy/pulse-the ion-recombination correction methods recommended by the International Atomic Energy Agency (IAEA) and the American Association of Physicists in Medicine (AAPM) are not appropriate, because they overestimate the correction factor. In this study, we suggest a practical ion-recombination correction method, based on Boag's improved model, and apply it to reference dosimetry for electron beams of about 100 mGy/pulse generated from an electron linear accelerator (LINAC). Methods: This study employed a theoretical model of the ion-collection efficiency developed by Boag and physical parameters used by Laitano et al. We recalculated the ion-recombination correction factors using two-voltage analysis and obtained an empirical fitting formula to represent the results. Next, we compared the calculated correction factors with published results for the same calculation conditions. Additionally, we performed dosimetry for electron beams from a 6 MeV electron LINAC using an Advanced Markus^® ionization chamber to determine the reference dose in water at the source-to-surface distance (SSD)=100 cm, using the correction factors obtained in this study. Results: The values of the correction factors obtained in this work are in good agreement with the published data. The measured dose-per-pulse for electron beams at the depth of maximum dose for SSD=100 cm was 115 mGy/pulse, with a standard uncertainty of 2.4%. In contrast, the k_s values determined using the IAEA and AAPM methods are, respectively, 8.9% and 8.2% higher than our results. Conclusions: The new method based on Boag's improved model provides a practical method of determining the ion-recombination correction factors for high dose-per-pulse radiation beams up to about 120 mGy/pulse. This method can be applied to electron beams with even higher dose-per-pulse, subject to independent verification.

• 대한방사선기술학회지:방사선기술과학
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• 제43권6호
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• pp.443-451
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• 2020

This study is to evaluate absorbed dose from right lung for brachytherapy and to estimate the effects of tissue heterogeneities on dose distribution for Iridium-192 source using Monte Carlo simulation. The study employed Geant4 code as Monte Carlo simulation to calculate the dosimetry parameters. The dose distribution of Iridium-192 source in solid water equivalent phantom including aluminium plate or steel plate inserted was calculated and compared with the measured dose by the ion chamber at various distances. And the simulation was used to evaluate the dose of gamma radiation absorbed in the lung organ and other organs around it. The dose distribution embedded in right lung was calculated due to the presence of heart, thymus, spine, stomach as well as left lung. The geometry of the human body was made up of adult male MIRD type of the computational human phantom. The dosimetric characteristics obtained for aluminium plate inserted were in good agreement with experimental results within 4%. The simulation results of steel plate inserted agreed well with a maximum difference 2.75%. Target organ considered to receive a dose of 100%, the surrounding organs were left the left lung of 3.93%, heart of 10.04%, thymus of 11.19%, spine of 12.64% and stomach of 0.95%. When the statistical error is performed for the computational human phantom, the statistical error of value is under 1%.