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本文探讨了SPECT/CT校准体模和重建方法的选择,以用于临床SPECT/CT的准确活度定量。分别对活度已知的点源、大圆柱、小圆柱3种校准体模进行SPECT/CT扫描,然后对每个断层数据依次采用4种重建方法(FBP、OSEM、OSEM+AC、OSEM+AC+SC)进行重建,并据此计算校准因子。将小圆柱作为活度定量的对象进行定量误差计算。OSEM+AC和OSEM+AC+SC的平均相对定量误差均小于10%,FBP和OSEM的平均相对定量误差均大于20%。OSEM+AC的平均相对定量误差在采用小圆柱做校准体模时与OSEM+AC+SC无显著差异,而在采用大圆柱和点源时,分别较OSEM+AC+SC的小3.38%和6.48%(P<0.05)。3种体模的对比中,采用OSEM+AC时差异不显著,采用其他重建方法时差异显著。采用OSEM+AC+SC时,小圆柱作校准体模的定量误差较大圆柱和点源的结果分别小3.92%和6.42%(P<0.05)。结果表明,基于CT和迭代算法的衰减校正可有效提升活度定量准确性,但散射校正的效果不佳;校准体模应尽可能与目标定量对象相似。合理选择校准体模和重建方法,可有效提升SPECT/CT的活度定量准确性。 相似文献
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放射治疗的X光透射剂量中含有不同强度的模体散射线,影响其临床应用.本文基于实验方法在不同条件下测量6 MV X线射野中心轴及离轴位置的透射剂量分布,从中提取原射线剂量,计算得到相应的散射线剂量,分析透射剂量中原射线和模体散射线的大小,研究不同条件下透射剂量中模体散射线分布的物理特性. 相似文献
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本文研究设计了一种用于获取γ辐照装置辐射场和货物剂量场真实分布的新型工作模体。基于真实γ辐照装置参数构建了有效可用的模拟辐射场,提出了新型工作模体的结构和填料设计方法。采用蒙特卡罗方法和随机填充方法(RCS)模拟计算剂量计套管材料与壁厚、填料小球尺寸、空心填料小球尺寸与壁厚、小球填充方式等影响模体剂量学性能的主要因素的分布规律。在满足计算置信度的前提下,参数优化取值范围为:套管采用壁厚为3~5 mm的铝管,对辐射场干扰不超过4.372 23%;填料选择外径为1~4 cm、壁厚为1.1~11.5 mm、材料等效性好、货物密度模拟范围为0.1~0.5 g/cm3的聚丙烯小球,对辐射场干扰不超过9.998 44%;均匀填充和随机填充模式对辐射场干扰基本持平,且均不超过10%。结果表明,当前设计可行有效,投入低、兼顾参数多且量程更宽,适合推广应用。 相似文献
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本文报道了γ射线外照射个人剂量估算的体模实验结果,给出了特定照射几何条件下的器官剂量、有效剂量当量与个人剂量计吸收剂量或人体中心自由空气场照射量的比值(DROP、DROT),并对事故剂量的种常用表达参量作了比较。 相似文献
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CT数据既是开展肿瘤精确放射治疗的基本数据,也是利用蒙特卡罗方法开展个体化剂量分布计算的主要数据。通过提取CT数据中的像素信息,进而转化为对应组织材料信息,重建得到个体化数字体模。利用所构建的数字体模,作了一些初步应用,结果表明基于CT数据获取的MCNP个体化体模正确,可为放疗计划的评估提供参考依据。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(9):964-971
Conversion from tooth enamel dose to organ doses was analyzed to establish a method of retrospective individual dose assessment against external photon exposure by electron spin resonance (ESR) dosimetry. Dose to tooth enamel was obtained by Monte Carlo calculations using a modified MIRD-type phantom with a teeth part. The calculated tooth enamel doses were verified by measurements with thermo-luminescence dosimeters inserted in a physical head phantom. Energy and angular dependences of tooth enamel dose were compared with those of other organ doses. Additional Monte Carlo calculations were performed to study the effect of human model on the tooth enamel dose with a voxel-type phantom, which was based on computed tomography images of the physical phantom. The data derived with the modified MIRD-type phantom were applied to convert from tooth enamel dose to organ doses against external photon exposure in a hypothesized field, where scattered radiation was taken into account. The results indicated that energy distribution of photons incident to a human body is required to evaluate precisely an individual dose based on ESR dosimetry for teeth. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):1049-1052
A voxel-based frog phantom has been developed for radiation protection of the environment. The voxel-based frog phantom was applied to evaluating self-absorbed fractions (self-AFs), which are defined as the fraction of energy emitted by a radiation source that is absorbed within the source organ. The self-AFs were evaluated for both photons and electrons in the spleen, kidneys, and liver using Monte Carlo simulations. Furthermore, self-S values (mGy/MBq.s) for 18F and 90Y in the organs were calculated using the results of the self-AFs. Consequently, the voxel-based frog phantom was found to be useful for the organ dose evaluations, which have not been proposed by the International Commission on Radiological Protection (ICRP). It was also confirmed that the self-AFs and self-S values are largely dependent on the mass of the source organ. 相似文献
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A new operating phantom was studied for obtaining the true distribution of the radiation field of the gamma irradiation facility and the dose field in the cargo container. An effective and usable simulated radiation field was constructed based on the parameter of the real gamma irradiation facility. The design method for the structure and padding of new operating phantom was proposed. The Monte Carlo method and random filling method (RCS) were adopted to simulate the distribution law of the main factor affecting the dosimetry parameters of the phantom body, such as the dosimeter sleeve material and wall thickness, filler ball size, hollow filler ball size and wall thickness, ball filling method, etc. Under the premise of satisfying the calculation confidence level, the optimization ranges of parameters are as follows: Aluminum tube with wall thickness of 3-5 mm is used as the sleeve, which interferes with the radiation field no more than 4.372 23%; Polypropylene sphere with outer diameter of 1-4 cm, wall thickness of 1.1-11.5 mm, cargo density simulating range of 0.1-0.5 g/cm3, and good material equivalence is selected as the phantom padding, which interferes with the radiation field no more than 9.998 44%; The interference level of the uniform and random filling modes on the radiation field is almost the same, and both are less than 10%. The results show that the current design is feasible and effective, with low investment, more parameters and wider range, and it is suitable for popularization and application. 相似文献
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为了精确评估核辐射环境下人体及器官受照剂量,FDS团队基于中国高精度辐射虚拟人模型Rad-HUMAN发展了体素级人体外照射剂量评估方法。但由于计算量巨大,现有计算流程和计算方法难以满足虚拟仿真对剂量评估实时性的要求。为了解决这一问题,本文借助OpenMP和MPI并行计算技术,发展了基于并行计算的体素级人体外照射剂量评估方法,实现了百万量级体素外照射剂量实时计算。以加速器驱动铅铋冷却反应堆堆顶包容小室内维修作业人体受照剂量评估为例的测试结果表明,该方法满足了体素级剂量实时评估计算的需求,对考虑到器官剂量限制的人体外照射剂量实时精确评估有重要意义。 相似文献
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X射线螺旋CT机不同扫描条件下,用有机玻璃均匀模体测量多层扫描的CT剂量指数值,用均匀水模体测量CT值的均匀性及其噪声。比较了不同扫描条件下,患者肺部肿块影及片状影的CT图像质量。结果表明:曝露量为40、25、7.5mAs时的CT剂量指数值分别不超过曝露量为115mAs时的40%、30%和15%。本文用CT扫描“优化因子”作为图像质量、病人所受剂量的综合评价指标,实现了CT扫描条件优化的定量分析。虽然,随X射线曝露量减少,均匀模体断层内CT值噪声增加、正常图像百分率下降,但从图像质量、病人剂量综合考虑,X射线胸部CT扫描的曝露量宜取25mAs。 相似文献