Dose coefficients of ICRP adult reference voxel phantom for internal dosimetry of selected radiopharmaceuticals using Geant4/GATE simulation.

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
S Kaddouch, N El Khayati
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引用次数: 0

Abstract

One of the main objectives of this internal dosimetry research is the evaluation of the absorbed dose in the target organs. This aim can be achieved by combining the Monte Carlo method with a voxelized phantom in a numerical simulation platform. In internal dosimetry, Monte Carlo method is recognized as the most efficient method for absorbed dose calculation. Several Monte Carlo codes have been developed for this purpose. Geant4/GATE is one of the existing Monte Carlo codes. In this context, we have chosen to evaluate the absorbed dose of some radiopharmaceuticals using the International Commission on Radiological Protection adult reference voxel phantom and Geant4/GATE. First, the specific absorbed fractions were estimated for photon sources from 10 keV to 10 MeV. Then, absorbed doses were calculated for some radionuclides. Therefore, dose coefficients were determined for 20 target regions for each radionuclide. The results were compared with the literature.

使用Geant4/GATE模拟选定放射性药物内剂量测定的ICRP成人参考体素幻影剂量系数。
体内剂量学研究的主要目的之一是评估靶器官的吸收剂量。在数值模拟平台上,将蒙特卡罗方法与体素化幻体相结合可以实现这一目标。在内剂量学中,蒙特卡罗法被认为是计算吸收剂量最有效的方法。为此目的开发了几个蒙特卡罗代码。Geant4/GATE是现有的蒙特卡罗代码之一。在这种情况下,我们选择使用国际放射防护委员会成人参考体素幻影和Geant4/GATE来评估一些放射性药物的吸收剂量。首先,估计了10 keV ~ 10 MeV光子源的比吸收分数。然后,计算了一些放射性核素的吸收剂量。因此,确定了每种放射性核素的20个靶区的剂量系数。结果与文献进行比较。
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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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