• 대한방사선기술학회지:방사선기술과학
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• 제39권4호
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• pp.571-575
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• 2016

본 연구에서는 몬테칼로 전산모사 코드인 GATE6 (Geant4 Application for Tomographic Emission ver.6)를 사용하여 의료용 선형 가속기인 Varian사의 Clinac 21EX를 모사하고, 6 MV 광자선의 선량 특성을 평가하였다. 몬테칼로 방법은 방사선 치료시 환자 내의 선량분포를 계산하는 가장 정확한 방법으로 널리 이용되고 있다. 몬테칼로 기반의 코드를 이용하여 선형가속기의 조사 헤드부를 통과하는 입자의 흐름을 모사하는 것은 조사선량을 정량화 하는데 필요한 입자들의 에너지, 공간 분포와 같은 임상적인 빔의 특성을 결정하기 위한 실용적인 방법이다. 본 연구에서 모사한 선형가속기의 조사 헤드부는 빔 경로에 위치한 타겟, 일차 콜리메이터, 선속 평탄 필터, 이온전리함, 이차 콜리메이터로 구성된다. 모사된 선형가속기를 이용하여 선원-표면간 거리 100 cm, 조사야 $10{\times}10cm^2$ 조건에서 물팬텀 내의 광자선 에너지 스펙트럼(energy spectrum), 심부선량백분율(percentage depth dose), 선량프로파일(dose profiles)을 측정하였으며, 이 결과값을 실험 측정값과 비교하여 정확성을 검증하였다. 본 연구에서는 모사를 통한 결과값과 실험값이 매우 일치함을 보였으며, 이를 통해 GATE6 전산모사 코드는 방사선치료에 사용되는 광자선을 모사하기에 효과적임을 입증하였다.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.301-309
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• 2022

This work aims to establish some X-ray qualities recommended by the International Standard Organization (ISO) using the half-value layer (HVL) and H_p(10) dosimetry approaches. The HVL values of the following qualities N-60, N-80, N-100, N-150 and N-250 were determined using various attenuation layers. The obtained results were compared to those of reference X-ray beam qualities and a good agreement was found (difference less than 5% for all qualities). The GAMOS (Geant4-based Architecture for Medicine-Oriented Simulations) radiation transport Monte Carlo toolkit was employed to simulate the production of X-ray spectra. The characteristics HVLs, mean energy and the spectral resolution of simulated spectra have been calculated and turned out to be conform to the ISO reference ones (difference less than the limit allowed by ISO). Furthermore, the conversion coefficients from air kerma to personal dose equivalent for simulated and measured spectra were fairly similar (the maximum difference less than 4.2%).

• 한국콘텐츠학회논문지
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• 제15권4호
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• pp.350-356
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• 2015

본 연구의 목적은 몬테칼로 모사방법을 이용하여 소동물 전용 양전자방출단층촬영 시스템의 모듈 내 섬광체 배열 수에 따른 특성평가를 하는 것이다. 이 연구에서 제안한 소 동물 전용 양전자방출단층촬영 시스템은 모듈 내 섬광체 수를 1 ~ 8개로 구성하였으며, 섬광체 크기는 $2.0{\times}2.0{\times}10.0mm^3$ 크기의 LSO섬광결정을 사용하였고 스캐너의 직경은 100 mm로 설계하였다. 몬테칼로 시뮬레이션 방법중에 하나인GATE 코드를 이용하여 선원은 511 keV 점선원을 이용하였으며 동시계수 측정된 좌표값을 이용하여 민감도 및 사이노그램을 획득하였다. 모듈 내 섬광체 수가 적을수록 모듈 별 틈새가 줄어들어 민감도가 향상되는 결과를 보였으며, 사이노그램 결과에서도 불완전한 데이터(missing data)가 발생하지 않는 것을 알 수 있었다. 이 연구 결과는 모듈 안 섬광체 수가 적을수록 민감도 향상 및 불완전한 데이터 획득이 줄어드는 것을 증명함으로써, 소동물 전용 양전자방출단층촬영 시스템의 성능 개선을 위한 새로운 접근법을 제시한다.

• Nuclear Engineering and Technology
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• 제51권2호
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• pp.533-538
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• 2019

The mechanical-collimation imaging is the most mature technology in prompt gamma (PG) imaging which is considered the most promising technology for beam range verification in proton therapy. The purpose of the present study is to compare the performances of two mechanical-collimation PG cameras, knife-edge (KE) camera and multi-slit (MS) camera. For this, the PG cameras were modeled by Geant4 Monte Carlo code, and the performances of the cameras were compared for imaginary point and line sources and for proton beams incident on a cylindrical PMMA phantom. From the simulation results, the KE camera was found to show higher counting efficiency than the MS camera, being able to estimate the beam range even for $10^7$ protons. Our results, however, confirmed that in order to estimate the beam range correctly, the KE camera should be aligned, at least approximately, to the location of the proton beam range. The MS camera was found to show lower efficiency, being able to estimate the beam range correctly only when the number of the protons is at least $10^8$. For enough number of protons, however, the MS camera estimated the beam range correctly, errors being less than 1.2 mm, regardless of the location of the camera.

• 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%.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1545-1556
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• 2020

Recently, the International Commission on Radiological Protection (ICRP) has developed the Mesh-type Reference Computational Phantoms (MRCPs) for adult male and female to overcome the limitations of the current Voxel-type Reference Computational Phantoms (VRCPs) described in ICRP Publication 110 due to the limited voxel resolutions and the nature of voxel geometry. In our previous study, the MRCPs were used to calculate the dose coefficients (DCs) for idealized external exposures of photons and electrons. The present study is an extension of the previous study to include three additional particles (i.e., neutrons, protons, and helium ions) into the DC library by conducting Monte Carlo radiation transport simulations with the Geant4 code. The calculated MRCP DCs were compared with the reference DCs of ICRP Publication 116 which are based on the VRCPs, to appreciate the impact of the new reference phantoms on the DC values. We found that the MRCP DCs of organ/tissue doses and effective doses were generally similar to the ICRP-116 DCs for neutrons, whereas there were significant DC differences up to several orders of magnitude for protons and helium ions due mainly to the improved representation of the detailed anatomical structures in the MRCPs over the VRCPs.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1495-1502
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• 2020

A new method of X-ray source spectrum estimation based on compressed sensing is proposed in this paper. The algorithm K-SVD is applied for sparse representation. Nonnegative constraints are added by modifying the L₁ reconstruction algorithm proposed by Rosset and Zhu. The estimation method is demonstrated on simulated spectra typical of mammography and CT. X-ray spectra are simulated with the Monte Carlo code Geant4. The proposed method is successfully applied to highly ill conditioned and under determined estimation problems with a good performance of suppressing noises. Results with acceptable accuracies (MSE < 5%) can be obtained with 10% Gaussian white noises added to the simulated experimental data. The biggest difference between the proposed method and the existing methods is that multiple prior knowledge of X-ray spectra can be included in one dictionary, which is meaningful for obtaining the true X-ray spectrum from the measurements.

• 한국우주과학회:학술대회논문집(한국우주과학회보)
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• 한국우주과학회 2004년도 한국우주과학회보 제13권2호
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• pp.347-350
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• 2004

A space radiation analysis has been used to evaluate an ability of electronic equipment boxes or spacecrafts to endure various radiation effects, so it helps design thicknesses of structure and allocate components to meet the radiation requirements. A comparison study of space radiation dose analysis programs SPENVIS Sectoring Tool (SST) and SIGMA II is conducted through some structure cases, simple sphere shell, box and representative satellite configurations. The results and a discussion of comparison will be given. A general comparison will be shown for understanding those programs. The both programs use the same strategy, solid angle sectoring with ray-tracing method to produce an approximate dose at points in representative simple and complex models of spacecraft structures. Also the particle environment data corresponding to mission specification and radiation transport data are used as input data. But there are distinctions between them. The specification of geometry model and its input scheme, the assignment of dose point and the numbers, the prerequisite programs and ways of representing results will be discussed. SST is a web-based interactive program for sectoring analysis of complex geometries. It may be useful for a preliminary dose assessment with user-friendly interfaces and a package approach. SIGMA II is able to obtain from RSICC (Radiation Safety Information Computational Center) as a FOR-TRAN 77 source code. It may be suitable for either parametric preliminary design or detailed final design, e.g. a manned flight or radiation-sensitive component configuration design. It needs some debugs, recompiling and a tedious work to make geometrical quadric surfaces for actual spacecraft configuration, and has poor documentation. It is recommend to vist RSICC homepage and GEANT4/SSAT homepage.