Gamma ray and neutron shielding capacity of and dosimetry of composite compounds with diagnostic and therapeutic energies
作者机构：Department of PhysicsImam Hossein Comprehensive UniversityTehranIran
出 版 物：《Radiation Detection Technology and Methods》 (辐射探测技术与方法（英文）)
年 卷 期：2024年第8卷第2期
页 面：1217-1228页
核心收录：
学科分类：07[理学] 070202[理学-粒子物理与原子核物理] 0702[理学-物理学]
主 题：Shielding Medical shielding Geant4 Gamma ray Radiation Dosimetry
摘 要：Purpose Ionizing radiation protection is one of the most fundamental research and application fields in reducing the absorbed dose of sensitive internal *** presence of lead as the first radiation shield with a series of good features,such as high density and having some flexibility,and a series of features such as toxicity,low physical and chemical stability and high weight has been thinking about replacing it for a long ***,in this research,we have investigated features of the ionizing radiation shielding of composite compounds without lead in the photon energy range of 15 keV to 15 *** To extract such features,it is necessary to use a computational *** this research,we have done all our calculations based on the Geant4 tool based on the Monte Carlo *** tool is a multi-purpose tool that can be used for particle transport calculations such as electrons,protons,neutrons,heavy charged particles and photons in different environments such as human *** We have calculated mass attenuation coefficient(MAC)by using the Monte Carlo simulations such as Geant4 tool,XMuDat and XCOM *** the continuation of the investigation of the protection feature,four laboratory energies have been selected and *** fact,the performance of shields against 60 keV,662 keV and 1.2 MeV sources has been *** this case,we have obtained the passing flux of photons,half-value layer(HVL),tenth-value layer(TVL)and mean free path(MFP).Then,the image of the passing photon flux of 241 Am(60 keV),^(137)Cs(662 keV)and^(60)Co(1.2 MeV)sources for a shielding sample is *** the aim is to examine the overall protection characteristics of the samples,we have considered the source as a neutron-gamma mixture and made of *** this case,the passing fux of photons and the ratio of neutrons passing through the shields are *** the continuation of the work,MIRD phantom has been used to check the performance of the shields in
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