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Comparison of neutron and secondary gamma dose assessment using polygon mesh and voxel computational phantoms

机译:使用多边形网状物和体素计算模拟中子和次级γ剂量评估的比较

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摘要

The newly developed mesh-type reference computational phantoms (MRCPs) represent the evolution of the previous reference phantoms and a more detailed description of the human body, addressing the voxel reference phantom limitations. These allow for a more accurate dose calculation in the human body, which in some cases results in a significant difference of the calculated quantities. In this work, the absorbed dose calculation due to neutrons and gammas was calculated using a voxel and a mesh-type computational phantom. The goal was to understand how a more accurate description of the human body affects the estimated neutron dose. The phantoms were tested in a real-case scenario: they were placed in front of a neutron Howitzer container model using PHITS. This model corresponds to the neutron Howitzer container at the Neutron Measurements Laboratory of the Energy Engineering Department of the Polytechnic University of Madrid (UPM), and at the time of measurement it was equipped with a Am-241-Be neutron source of 74 GBq in its center. The container allows the source to be in either the irradiation or the storage position. Results show that when dealing with neutrons, the dose deviation when using GOLEM or the MRCP leads to a general 20%-30% deviation that goes up to above 400% in small thin structures such as the eye.
机译:新开发的网格型参考计算模拟(MRCPS)代表了先前参考模拟的演变和人体的更详细描述,解决了体素参考模拟限制。这些允许在人体中进行更准确的剂量计算,在某些情况下,在某些情况下导致计算量的显着差异。在这项工作中,使用voxel和网格型计算幻影计算由于中子和γ引起的吸收剂量计算。目标是了解人体的更准确描述如何影响估计的中子剂量。在实际情况下,幽灵进行测试:使用料点放置在中子榴弹炮容器模型的前面。该型号对应于马德里大学(UPM)的能量工程系中子测量实验室中子测量实验室,在测量时,它配备了AM-241-中子来源74 GBQ它的中心。容器允许源处于照射或存储位置。结果表明,在处理中子时,使用加魔或MRCP时的剂量偏差导致一般的20%-30%偏差,其小薄型诸如眼睛的小型结构上高于400%。

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