• 한국방사선학회논문지
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• 제17권5호
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• pp.641-649
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• 2023

본 연구에서는 3D 프린팅 기술을 활용하여 제작한 차폐체의 성능을 비교 분석하여, 고에너지 전자선 치료 시 차폐체로서의 적용 가능성에 대해 알아보고자 한다. 고에너지 전자선에 대한 3D 프린팅 재료의 차폐성능 평가를 위해 실측과 몬테카를로 기반의 모의실험을 수행하였다. 첫 번째, 모의실험에 대한 신뢰성 확보를 위해 IAEA의 TRS-398 권고를 참조하여 선원항 평가를 수행하였다. 두 번째, PLA+W (93%) 재료에 대한 차폐 성능 분석을 위해 3D 프린터를 이용하여 시편을 제작하였고, 전자선 에너지에 따른 두께별 차폐율을 평가하였다. 세 번째, PLA+W (93%)와 기존 차폐체 간 차폐 성능 비교 분석을 통해 전자선 치료 시 필요한 차폐 두께를 산정하였다. 연구 결과, 첫 번째, 실측과 모의실험을 통한 선원항 평가 결과, 1% 이내의 오차로 TRS-398 권고를 만족하여 모의실험에 대한 신뢰성을 확보하였다. 두 번째, PLA+W (93%)에 대한 차폐 성능 분석 결과, 6 MeV 전자선은 3.12 mm에서 95% 이상의 차폐율을 나타냈고, 15 MeV 전자선은 10 mm 두께에서 90% 이상의 차폐율을 나타내었다. 세 번째, 모의실험을 통해 PLA+W (93%) 재료와 기존 차폐체 간 비교 분석을 통해 동일 두께 내에서 텅스텐, 납, 구리, PLA+W (93%), 알루미늄 순서로 차폐율이 높은 결과를 나타내었으며, 6 MeV 전자선은 5 mm 이상, 15 MeV 전자선은 10 mm 이상 두께에서 거의 유사한 차폐율을 나타내었다. 향후 본 연구를 통해 고에너지 전자선 치료 시 PLA+W (93%) 재료를 이용한 환자의 맞춤형 차폐체 제작을 위한 기초자료로서 활용될 수 있을 것으로 판단된다.

• 한국방사선학회논문지
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• 제17권2호
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• pp.215-221
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• 2023

수정체가 포함된 Brain CT 스캔 조건 중 관전압을 80, 100, 120 kVp로 변화시켜 적용하고 납, 납 고글, 황산바륨 실리콘 혼합 차폐체를 이용하여 선량의 변화를 분석하고, 차폐체가 화질에 영향을 미치는 정도를 SNR, CNR, SSIM 지수 분석방법을 적용하여 비교 분석해 보았다. 그 결과 모든 차폐물질 적용으로 선량 감소는 하였지만, 선량 감소 차는 크지 않은 것으로 분석되었다(P > 0.05). 또한 차폐물질 적용으로 화질의 변화는 납 고글 적용 시 SNR, CNR이 가장 높았고 SSIM 분석에서도 기준값 1에 가장 근접하여 구조적 유사도가 가장 우수한 것으로 측정되었다. 따라서, 본 연구결과를 기준으로 더욱 다양한 차폐체 적용과 임상실험 결과를 도출하여 적용한다면 차폐체 활용 검사 시 임상 적용기준에 도움을 줄 수 있을 것으로 사료된다.

• Journal of Electrical Engineering and Technology
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• 제13권2호
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• pp.936-942
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• 2018

The diagnostic multi-leaf collimator preventing unnecessary dose from entering into patients during the diagnostic examination was made in this study. The movement of the entire 50 leaves was embodied with the group of 25 ones thereof configured in a pair facing each other on the left and right of the median line. Dimensions of the length, width, and height of each shielding leaf were $5{\times}0.5{\times}0.5cm^3$ resulting in the maximum boost field of $10{\times}10cm^2$. The material of multi-leaf collimator had the excellence on the machinability with the use of the SKD-11 alloy tool steel having the high wear resistance against frequent movement, and it was devised to control both-side's shielding leaves by moving 2 motors unlike existing remedial multi-leaf collimator that use as many motors as the number of 50 shielding leaves. Thereafter, the transmission dose of leaves, cross-leaf leakage dose, and inter-leaf leakage dose were measured by the developed multi-leaf collimator attached to X-ray equipment. An ionization chamber was used to detect doses there from, and the comparative analysis was carried out by means of the radiographic film that was easy to detect the dose leakage in between each leaf. Results obtained from the test conducted in comparative analysis yielded approximately 98%, 96%, and 94% of shielding efficiency realized at each level of energy of 80kV, 100kV, and 120kV it was confirmed there was no dose leakage resulted from the varied level of irradiation energy. Thus the multi-leaf collimator to be developed based on this study is thought that it could fully reduce the unnecessary dose to patients in the diagnostic test and the shielding efficiency thereof is expected to be increasing if it is made in a miniaturized form with a way of increasing the thickness of each leaf later for an extended application to general diagnostic purposes.

• Radiation Oncology Journal
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• 제12권2호
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• pp.253-262
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• 1994

The patterns of the conventional radiation treatment fields and their shielding blocks are analysed to determine the optimal dimension of the MultiLeaf Collimator (MLC) which is considered as an essential tool for conformal therapy. Total 1109 radiation fields from 303 patients (203 from Asan Medical center, 50 from Baek Hosp and 50 from Hanyang Univ. Hosp.) were analysed for this study. Weighted case selection treatment site (from The Korean Society of Therapeutic Radiology 1993). Ninety one percent of total fields have shielding blocks. Y axis is defined as leaf movement direction and it is assumed that MLC is installed on the cranial-caudal direction. The length of X axis were distributed from 4cm to 40cm (less than 21cm for $95\%$ of cases), and Y axis from 5cm to 38cm (less than 22cm for $95\%$ of cases). The shielding blocks extended to less than 6cm from center of the field for $95\%$ of the cases. Start length for ninety five percent of block is less than 10cm for X axis and 11cm for Y axis. Seventy six percent of shielding blocks could be placed by either X or Y axis direction, $7.9\%$ only by Y axis, $5.1\%$ only by X axis and It is reasonable to install MLC for Y direction. Ninety five percent of patients can be treated with coplanar rotation therapy without changing the collimator angle. Eleven percent of cases of cases were impossible to replace with MLC. Futher study of shielding technique is needed for $11\%$ impossible cases. The treatment field dimension of MLC should be larger than $21cm{\times}22cm$. The MLC should be designed as a pair of 21 leaves with 1cm wide for an acceptable resolution and 17cm long to enable the leaf to overtravel at least 6cm from the treatment field center.

• 한국방사선학회논문지
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• 제13권1호
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• pp.45-53
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• 2019

본 연구는 의료용 선형가속기 시설을 차폐하는 콘크리트에 대한 중성자 방사화 연구로써, 일반 콘크리트와 저 방사화 콘크리트를 비교 분석하였다. 실험 방법은 MCNPX (Ver. 2.5.0)와 FISPACT-2010를 사용하여 모의실험을 진행하여, 광자선과 중성자선에 대한 차폐능을 산정하고 중성자 방사화 평가를 진행하였다. 그 결과 차폐능은 일반 콘크리트에서 20~50 cm 효율적이였으며, 방사화 평가의 경우 저 방사화 콘크리트에서 방사능이 낮게 계산되었으나, 모두 자체처분허용 농도를 초과하지 않는 수준으로 산정되었다. 이를 종합적으로 분석한 결과 일반 콘크리트를 사용하는 것이 효율적인 것으로 판단된다.

• 한국방사선학회논문지
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• 제12권2호
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• pp.173-178
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• 2018

병원에서 방사선을 차폐하는데 있어 납은 매우 유용하게 사용되고 있다. 하지만 납은 독성을 가지고 있고 대체물질에 대한 연구가 많이 이루어지고 있으며, 대표적으로 텅스텐을 대체물질로 한 연구가 많이 이루어지고 있다. 이에 본 연구에서 납과 텅스텐의 물리적 특성 및 반가층 실험을 진행한 결과 원자번호가 높은 납 원소의 반응단면적이 텅스텐에 비해 높게 나타났으나, 텅스텐의 밀도가 높아 동일한 크기일 경우 텅스텐의 전자밀도가 납에 비해 약 1.7배 높은 것으로 나타났다. MCNPX를 이용한 모의 모사에서도 에너지 따라 다소 차이가 있지만 텅스텐이 납에 비해 약 1.4배 차폐효과가 높은 것으로 나타났으며, 텅스텐이 납에 비해 우수한 차폐효율을 갖고 있는 것으로 확인 되었다. 하지만 경제적 측면을 고려할 때 텅스텐은 희소금속으로 납에 비해 가격이 약 25배 높아 납에 대한 대체물질로는 부적당한 것으로 사료되었다.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.1062-1070
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• 2022

In the present communication, pure and stable α-Bismuth Oxide (Bi₂O₃) nanoparticles (NPs) were synthesized by low temperature solution combustion method using urea as a fuel and calcined at 500℃. The synthesized sample was characterized by using powder X-ray Diffraction (PXRD), Scanning Electron Microscopy (SEM), Energy dispersive X-ray analysis (EDAX), Transmission Electron Microscopy (TEM), Fourier Transform Infrared Spectroscopy (FTIR) and UV-Visible absorption spectroscopy. The PXRD pattern confirms the formation of mono-clinic, stable and low temperature phase α-Bi₂O₃. The direct optical energy band gap was estimated by using Wood and Tauc's relation which was found to be 2.81 eV. The characterized sample was studied for X-ray/gamma ray shielding properties in the energy range 0.081-1.332 MeV using NaI (Tl) detector and multi channel analyzer (MCA). The measured shielding parameters agrees well with the theory, whereas, slight deviation up to 20% is observed below 356 keV. This deviation is mainly due to the influence of atomic size of the target medium. Furthermore an accurate theory is necessary to explain the interaction of X-ray/gamma ray with the NPs.The present work opens new window to use this facile, economical, efficient, low temperature method to synthesize nanomaterials for X-ray/gamma ray shielding purpose.

• 한국정보통신학회논문지
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• 제24권9호
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• pp.1132-1137
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• 2020

유방 X선 촬영 장치를 이용한 유방 촬영을 실시할 때 발생되는 불필요한 피폭 선량을 경감시키기 위해 비스무스로 제작한 차폐체를 촬영 부위의 반대 측 유방에 적용했을 때 차폐율 분석을 실시하였다. 오른쪽, 왼쪽을 압박하였을 때 CC와 MLO 검사 시 압박되지 않는 유방의 산란 선량을 알아보기 위하여 비스무스를 차폐하지 않았을 때(Not used : NU그룹)와 차폐했을 때(Used : U그룹)로 구분하여 실험을 진행하였다. NU 그룹의 평균선량은 9.568μSv이었고, U그룹의 평균 선량은 1.038μSv이었다. 비스무스 차폐체 사용 전후의 평균 측정 선량은 89.15% 감소되었다. 유방 촬영용 비스무스 차폐체를 사용하면 산란 방사선을 차폐하여 방사선에 의한 노출을 최소한으로 유지할 수 있다.

• 대한방사선기술학회지:방사선기술과학
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• 제42권6호
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• pp.477-482
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• 2019

Recently, due to the increased use of medical radiation, the radiation exposure of radiation workers should be considered as well as medical exposure of patients. And it is recommended to close the door during radiography. however, In this study, when the door was inevitably opened for radiography, the proposed method was to install the shield as a method of reducing the exposure dose. And its efficiency was analyzed. In simple chest radiography, the measurement point was changed according to the measurement location. Dose rate were measured 10 times for each condition using a dosimeter. And the average value was derived. Using this, the change of dose according to the opening and closing of the door and the installation of the shield was analyzed. Using this, we compared and analyzed the dose change according to the door opening and closing and the installation of the shield, and significance was verified through the SPSS ver. 24. Depending on whether the door was opened or closed, 11,215.35%, 159.0%, 101.9% increased in front of the door in the consol room, behind the wall and behind the lead glass. Depending on the installing of the shield, the 49.2%, 29.6%, 19.9%, 30.6% decrease in front of the door in the examination and consol room, behind the wall and lead glass. In addition, statistical analysis was showed that there were significant differences in both the results according to whether the door was opened or closed and shielding(p<.05). Close the door during radiography. However, when the door should be opened, it was confirmed that the dose rate were reduced by installing the shield. Therefore, to optimize radiation protection, it is recommended to install shields when opening the door.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.3051-3057
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• 2021

The concrete is considered as an important radiation shielding material employed widely in nuclear reactors, particle accelerators, laboratory hot cells and other different radiation sources. The present research is dedicated to the shielding properties study of the ordinary concrete reinforced with different weight fractions of lead oxide micro/nano particles. Lead oxide particles were fabricated by chemical synthesis method and their properties including the average size, morphological structure, functional groups and thermal properties were characterized by XRD, FESEM-EDS, FTIR and TGA analysis. The gamma ray mass attenuation coefficient of concrete composites has been calculated and measured by means of the Monte Carlo simulation and experimental methods. The simulation process was based on the use of MCNP Monte Carlo code where the mass attenuation coefficient (μ/ρ) has been calculated as a function of different particle sizes and filler weight fractions. The simulation results showed that the employment of the lead oxide filler particles enhances the mass attenuation coefficient of the ordinary concrete, drastically. On the other hand, there are approximately no differences between micro and nano sized particles. The mass attenuation coefficient was increased by increasing the weight fraction of nanoparticles. However, a semi-saturation effect was observed at concentrations more than 10 wt%. The experimental process was based on the fabrication of concrete slabs filled by different weight fractions of nano lead oxide particles. The mass attenuation coefficients of these slabs were determined at different gamma ray energies using ²²Na, ¹³⁷Cs and ⁶⁰Co sources and NaI (Tl) scintillation detector. The experimental results showed that the HVL parameter of the ordinary concrete reinforced with 5 wt% of nano PbO particles was reduced by 64% at 511 keV and 48% at 1332 keV. Reasonable agreement was obtained between simulation and experimental results and showed that the employment of nano PbO particles is more efficient at low gamma energies up to 1Mev. The proposed concrete is less toxic and could be prepared in block form instead of toxic lead blocks.