中国女性参考人曲面模型的光子有效剂量转换系数计算

本文基于人体断层解剖图像,根据所建立的中国女性参考人曲面模型和体素模型,采用MCNP计算了6种标准照射方式下光子在0.01~10MeV能量范围内20个能量点的光子有效剂量转换系数,并对曲面模型和体素模型的计算结果进行了比较。结果表明:在不同照射方式下曲面模型和体素模型的光子有效剂量转换系数的变化趋势基本一致,大部分能量点其差异在10%之内。光子有效剂量转换系数的差异主要是由于模型器官的位置和质量对剂量有一定影响,在低能级下差异较为明显。     

干旱地区核设施周围陆生昆虫—蒙古束颈蝗剂量系数估算

为了研究我国干旱地区核设施附近代表性生物剂量系数,以蒙古束颈蝗(Splingonotus mongolicus Saussure)为例,基于解剖学和几何学建立简化解剖学模型和基于CT断层扫描、Photoshop软件及Python编程等建立体素模型,并分别计算环境介质中⁹⁰Sr、¹³⁷Cs对蒙古束颈蝗不同组织和器官的内外照射剂量系数。为了验证本次计算结果的可行性,将计算结果与ICRP 108号报告进行了比较。由于ICRP 108号出版物采用整体简化模型,因此本文计算结果采用各个器官剂量系数总体平均值。结果显示:⁹⁰Sr对蒙古束颈蝗简化解剖学模型内外照射剂量系数分别为6.59×10^-4μGyh^-1/Bqkg^-1、6.74×10^-4μGyh^-1/Bqkg^-1;¹³⁷Cs对蒙古束颈蝗简化解剖学模型内外照射剂量系数分别为1.34×10^-4μGyh^-...     

基于并行技术的人体外照射实时精确剂量评估方法

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。     

用于生物剂量评价的体素模型建立及验证

以鲤鱼为例建立体素模型,计算水中137Cs对鲤鱼不同组织和器官的外照射剂量转换因子,并与建立的与体素模型尺寸相一致的简化模型、欧盟非人类物种评价方法 ERICA、ICRP 108号报告中参考生物淡水鱼的剂量转换因子估算结果进行了比较。结果显示,在本文的建模条件下,体素模型计算所得的总的剂量转换因子与简化模型的总剂量转换因子的结果接近,低于ICRP 108号报告和ERICA方法所提供的剂量转换因子的结果。     

一个中国成年女性体素模型的建立及辐射剂量学应用

开发了一个基于中国女性彩色解剖断层图像的体素剂量学模型VPCF,并用FLUKA程序计算了光子能量在0.02～10 MeV范围内的20个能量点、外照射方向为腹背向(AP)、背腹向(PA)的组织或器官剂量转换因子和有效剂量转换系数,并与ICRP 74号报告的推荐值、CRAM和Regina的计算值进行了比较.结果表明:VPCF有些器官(如膀胱)的剂量转换因子与ICRP 74号出版物差别较大;有效剂量转换系数的差别不如器官或组织的剂量转换因子明显;VPCF的有效剂量转换系数要大于ICRP 74号出版物推荐值、CRAM和Regina的计算值.     

GATE在计算人体体素模型光子剂量转换系数的应用分析

分析GEANT4应用发射断层(GEANT4 Application for Tomographic Emission,GATE)在模拟人体体素模型剂量转换系数的应用,为计算基于体素模型的光子辐射场中的剂量提供一种新路径。GATE是基于GEANT4开发并广泛应用于模拟正电子发射断层成像(Positron Emission Tomography,PET)、单光子发射计算机断层成像(Single Photon Emission Computed Tomography,SPECT)等成像系统以及放射治疗的蒙特卡罗模拟软件。用自编的MATLAB程序将人体体素模型KTMAN-2的体素数据逆转为断层影像(Computed Tomography,CT),再由VV软件将CT转换为GATE体素模型文件,在GATE和MCNPX(Monte Carlo N-Particle e Xtended)中模拟6种标准照射方式下、0.01~10 Me V能量范围内23种单能光子在人体内的输运,得到一系列的光子器官剂量转换系数,将两者的计算结果进行对比,并将结果和ICRP 74、ICRP 116号出版物的推荐值进行比较。GATE和MCNPX的计算结果具有很好的一致性,除质量很小的器官(垂体、扁桃体、甲状腺等),其它器官的差异都在3%以内;对于某些器官在某些照射条件下,所得结果和ICRP 74、ICRP 116号出版物的推荐值一致,但在某些照射条件本文结果与ICRP 74、ICRP 116出版物的推荐值存在较大差异。GATE为基于体素模型的剂量计算提供了一种新方法;本文计算的剂量转换系数对于分析亚洲人个体与ICRP参考人之间光子剂量转换系数的差异具有重要意义。     

辐射防护用中国参考人体素模型建立、应用及最新进展

以中国女性参考人体素模型为例,介绍了中国成年男女参考人体素模型的建立工作,包括构建非均匀骨模型,补充辐射敏感器官,进行器官二次分割和调整等过程。最后建立的中国参考人体素模型基本包含了ICRP新建议书中所有辐射敏感器官,器官质量与中国参考人数据差异基本在5%以内。该模型在内照射、外照射方面均得到一定应用,研究结果为我国辐射剂量评价工作提供了基础数据。最后介绍了人体体素模型的最新进展:精细乳房模型和微观骨模型。     

辐射防护用中国参考人体素模型建立、应用及最新进展北大核心CSCD

以中国女性参考人体素模型为例,介绍了中国成年男女参考人体素模型的建立工作,包括构建非均匀骨模型,补充辐射敏感器官,进行器官二次分割和调整等过程。最后建立的中国参考人体素模型基本包含了ICRP新建议书中所有辐射敏感器官,器官质量与中国参考人数据差异基本在5%以内。该模型在内照射、外照射方面均得到一定应用,研究结果为我国辐射剂量评价工作提供了基础数据。最后介绍了人体体素模型的最新进展:精细乳房模型和微观骨模型。     

中国成年女性精细乳房模型的建立及其在外照射防护中的应用

乳腺是对辐射致癌最敏感的器官之一,2007年国际放射防护委员会(ICRP)将乳腺的组织权重因子由0.05提升为0.12,使乳腺剂量的准确评估变得更为重要。本文利用数学建模方法建立了精细乳房模型,包括输乳窦、输乳管、小叶和脂肪组织,模型体素化后与中国成年女性参考人体素模型进行了融合。利用该模型计算了光子AP照射时乳腺腺体的剂量转换系数,并与原来模型的计算结果进行对比。结果显示,光子能量较低时两个模型的计算结果相差30%,光子能量在0.03 MeV以上时差别不大。     

基于面元模型的河蚌剂量转换系数的计算

基于河蚌开口与闭合两种形态,利用多边形网格(PM)与NURBS曲线技术对河蚌体素模型进行光滑和变形处理,分别建立河蚌开口面元模型和闭合面元模型,并通过MCNPX模拟计算河蚌在两种模型形态下的外照射剂量转换系数(外照射DCC)与内照射剂量转换系数(内照射DCC)。通过模拟结果可得出:(1)在外照射条件下,河蚌的外照射DCC的关系为:开口面元模型>闭合面元模型;(2)在内照射条件下,河蚌的内照射DCC的关系为:闭合面元模型>开口面元模型。     

Dose conversion coefficients for Chinese reference adult male and female voxel phantoms from idealized neutron exposures

A whole-body voxel phantom called CRAF representing the Chinese adult female was constructed in this study from color photographs. The CRAF has a height of 160 cm and a weight of 54 kg with 80 organs and tissues, including almost all organs required in the ICRP Publication 103. Masses of all organs in CRAF are consistent with the Chinese reference data within 1%. Our research group has previously developed a Chinese reference adult male phantom called CRAM, which has a height of 170 cm and a weight of 60 kg with 80 tissues and organs. A new set of fluence-to-dose conversion coefficients based on the Chinese reference adult voxel phantoms CRAM and CRAF are presented for six idealized external neutron exposures from 10^?8 MeV to 20 MeV. The calculation of organ-absorbed doses and effective doses were performed with the Monte Carlo transport code MCNPX 2.4. The resulting dose conversion coefficients were compared with those published in ICRP Publication 116, which represents the reference Caucasian. It was observed that the two sets of organ-absorbed dose conversion coefficients agreed well for most organs in ROT and ISO geometry; however, considerable deviations were found in some organs in AP, PA, RLAT and LLAT exposures. Organ-absorbed dose coefficients difference showed good agreement with the difference of organ depth distribution between Chinese and ICRP phantoms. For neutrons with energies above 2 MeV, the effective dose conversion coefficients of Chinese reference adult are almost identical to those of ICRP Publication 116 in AP, PA, ROT and ISO geometries, while are generally 15% higher than those of ICRP Publication 116 from lateral geometries. When energies range from 10^?8 MeV to 1 MeV, differences are within 10% in AP (–5%), PA (–8%) and ROT (4%) geometries; however, relatively large discrepancies are shown in lateral and ISO geometries, with differences of 15% for LLAT, 20% for RLAT and 12% for ISO, respectively.     

女性蹲姿曲面模型光子外照射剂量研究

基于中国女性参考人曲面模型建立女性蹲姿曲面模型,采用蒙特卡罗方法,针对6种标准光子外照射几何,计算光子能量0.01～10 MeV范围内21个能量点的器官吸收剂量转换系数和有效剂量转换系数,并与直立姿势的剂量数据进行了对比。结果表明:两种姿势中某些器官的吸收剂量转换系数在前后、后前以及侧向照射方式下差异较大。其中,后前照射方式下,光子能量为0.03 MeV时,乳腺的吸收剂量转换系数比直立姿势高115.1%。在不同照射方式下,大部分能量点的有效剂量转换系数的差异在10%范围内。转换系数的差异主要是由于胳膊和腿位置的改变,以及蹲姿时因身体前倾造成器官在照射方向上厚度发生改变而产生的。     

Conversion from Tooth Enamel Dose to Organ Doses for Electron Spin Resonance Dosimetry

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.     

核素153Sm体素S因子特性的研究

基于体素S因子计算个体化病例的三维剂量是目前核医学研究的一个重要方向.153Sm是目前骨转移治疗常用的核素之一.本文利用EGS4蒙特卡罗程序包构建了基于体素的三维吸收剂量分布模拟程序,计算了不同情况下153Sm的S因子,探讨了介质成分和物理密度对S因子的影响.结果表明:1)不同物理密度对S因子有明显影响;2)在相同物理密度的情况下,不同介质对S因子的影响相对较小.计算结果为基于体素S因子计算核素治疗的三维剂量提供了参考,明确了在不考虑介质和物理密度差异时S因子的误差.     

Experimental Estimation of Effective Dose for Irradiation Geometries in Working Places According to ICRP 1990 Recommendations

Conversion coefficients for the equivalent dose in tissue or organ and the effective dose were estimated experimentally with BeO-TLDs inside a male RANDO phantom against external photon radiation. The experiments were performed for Superior-Inferior and Inferior-Superior geometries in cases of unusual irradiation conditions which were occasionally seen in high radiation areas. For these geometries, a parallel photon beam to the long axis of phantom was irradiated. To evaluate the shielding effect of legs in the Inferior-Superior geometry, measurements with and without legs were done by linking a leg phantom, made of tissue equivalent material. The difference of effective dose by the leg phantom was found to be about 20% in the energy range studied.

The effective dose was calculated from the equivalent dose in tissues or organs by modifying the tissue weighting factors given in ICRP Publ. 60 for males, and the effective dose equivalent according to ICRP Publ. 26 was also derived to be compared with the effective dose. In this experiment, the effective dose was estimated lower than the effective dose equivalent about 40% for Superior-Inferior geometry and about 20% for Inferior-Superior geometry due to the change in tissue weighting factors. However, there was no remarkable difference for Anterior-Posterior geometry.     

A hybrid voxel sampling method for constructing Rad-HUMAN phantom

An accurate and fast sampling method was developed on the modeling of a voxel phantom called RadHUMAN for radiation protection of MC-based radiation transport and simulation.The segmented organ voxels,which were assigned with three dimensional(3D) coordinates,were simplified through a two-step hybrid sampling algorithm.Firstly,certain voxels were sampled into a coordinate matrix by the nearest neighbor sampling.Secondly,the coordinate matrix was renewed using a weighted sampling.To compare visualization with the sampling,the resultant matrix was used to extract the contour of organs/tissues for constructing polygon-surface phantom.The feasibility and effectiveness of the sampling method was vcriiied through the modeling of large organs(e.g.skeleton system) and application of transformation to MC computational geometries.     

Development of a compact high resolution gamma-ray detector for E-CT applications

A compact gamma-ray detector with good spatial resolution for emission computed tomography (E-CT) applications has been developed. The detector is composed of NaI(Tl) scintillation pixels array and Hamamastu R2486-05 PSPMT. Having a pixel size of 2 mm × 2 mm and an overall dimension of 48.2 mm × 48.2mm × 5 mm, it has 484 pixels in a 22×22 matrix. An average spatial resolution of 2.5mm (FWHM) was achieved. The slope of position linearity is constant within 10% in a range of 40mm. After corrections, the average value of differential non-linearity and absolute non-linearity were 0.16mm and 0.535mm respectively, and a 17% at FWHM of total energy resolution for 241Am was obtained.     

Implementation of Japanese Male and Female Tomographic Phantoms to Multi-particle Monte Carlo Code for Ionizing Radiation Dosimetry

Japanese male and female tomographic phantoms, which have been developed for radio-frequency electromagnetic-field dosimetry, were implemented into multi-particle Monte Carlo transport code to evaluate realistic dose distribution in human body exposed to radiation field. Japanese tomographic phantoms, which were developed from the whole body magnetic resonance images of Japanese average adult male and female, were processed as follows to be implemented into general purpose multi-particle Monte Carlo code, MCNPX2.5. Original array size of Japanese male and female phantoms, 320x160x866 voxels and 320x160x804 voxels, respectively, were reduced into 320x160x433 voxels and 320x160x402 voxels due to the limitation of memory use in MCNPX2.5. The 3D voxel array of the phantoms were processed by using the built-in repeated structure algorithm, where the human anatomy was described by the repeated lattice of tiny cube containing the information of material composition and organ index number. Original phantom data were converted into ASCII file, which can be directly ported into the lattice card of MCNPX2.5 input deck by using in-house code. A total of 30 material compositions obtained from International Commission on Radiation Units and Measurement (ICRU) report 46 were assigned to 54 and 55 organs and tissues in the male and female phantoms, respectively, and imported into the material card of MCNPX2.5 along with the corresponding cross section data. Illustrative calculation of absorbed doses for 26 internal organs and effective dose were performed for idealized broad parallel photon and neutron beams in anterior-posterior irradiation geometry, which is typical for workers at nuclear power plant. The results were compared with the data from other Japanese and Caucasian tomographic phantom, and International Commission on Radiological Protection (ICRP) report 74. The further investigation of the difference in organ dose and effective dose among tomographic phantoms for other irradiation geometries should be carried out by employing additional tomographic phantoms to find out the dosimetric difference of Asian human phantoms from Caucasian-based phantoms.