基于体素模型的光子外照射大鼠器官剂量模拟计算

获得外照射条件下的大鼠器官剂量,对于放射医学剂量-效应关系研究具有重要意义。本文基于大鼠微型CT图像建立大鼠体素模型,并研究光子外照射情况下大鼠器官剂量。大鼠体素模型质量323.7 g,单个体素尺寸为0.16 mm×0.16 mm×2 mm,包含大鼠大部分关键器官和组织。利用蒙特卡罗模拟程序MCNP计算获得了4种照射几何条件、21个单能(10 keV～10 MeV)平行光子束外照射情况下的器官剂量转换系数,最后对器官剂量随光子能量的变化进行了分析与讨论。     

基于ICRP141号报告模型计算吸入241Am后的排泄份额及剂量的对比分析

依据更丰富的受照人员实测数据,以国际放射防护委员会(ICRP)141号报告呼吸道模型及系统模型为代表的新模型及剂量转换系数相比旧模型及剂量转换系数具有更高可信度。对于目前超铀核素吸入后的基于间接测量的内照射评价来说,新、旧模型带来的计算结果的异同很重要。本文基于ICRP 141号报告为代表的新生物动力学模型建立超铀核素的滞留、排泄份额计算程序,并分别对工作参考人吸入S、M、F类²⁴¹Am气溶胶(AMAD 5 μm)后的尿、粪排泄份额进行新、旧模型计算值对比,发现了新、旧模型计算值的显著差异,且基于尿、粪样中²⁴¹Am估算有效剂量上,新、旧模型计算结果的差异也显著。基于尿粪的间接测量的内照射评价标准后期可视情况根据新模型计算值进行修订。     

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.     

α内外照射效率的转换系数

在细粒热释光测定年代中，真实的α剂量必须被转换成与β等效的内照射剂量，这个转换由α内照射效率Ｋ值完成。但对每个样品来说，这个Ｋ值是无法测定的，能测到的只是每个样品的α外照射效率Ｋ３．７，为此，研究了α内，外照射效率的转换系数以及测定的方法。结果表明，与石英近似的ＣａＳＯ４ｒ的α内外照射效率的转换系数在考古样品中为０．８４７，与理论计算值０．８５很一致。     

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^-...     

人类入侵景象下的处置库安全评价分析

利用剂量计算和风险评估模型,基于国际原子能机构(IAEA)推荐的标准数据库和日本核燃料循环开发机构(JNC)的玻璃固化体源项数据,利用程序计算了人类入侵处置库景象下的受照剂量和风险,计算结果表明:在人类入侵景象下,最大外照射剂量在10-4数量级,贡献较大的核素有126 Sn、243 Am;最大内照射剂量在101数量级,贡献较大的核素有240 Pu、241 Am、237 Np和243 Am;内照射和外照射的最大风险值在10-12数量级,远远低于其他类型风险。     

我国南方某核厂址蟾蜍剂量率评估的比较研究

选择我国南方某核厂址两栖动物——蟾蜍作为参考生物,建立了蟾蜍的生物解剖学模型和外照射环境模型。采用蒙特卡罗模拟技术计算源介质中放射性核素¹³⁷Cs、⁹⁰Sr和²³⁹Pu对靶组织/器官的辐射剂量率,由此计算蟾蜍整体的辐射剂量率。采用ERICA程序和RESRAD-BIOTA程序计算蟾蜍的剂量率,并与解剖学模型进行比较。结果表明:三种方法计算的蟾蜍内照射剂量率基本一致;由于外照射环境模型的不同,外照射剂量率估算结果并不相同,ERICA程序与解剖学模型计算的外照射剂量率结果更接近;解剖学模型关注生物组织/器官的辐射剂量,对于核素分布不均匀的生物个体研究具有重要的意义。     

吸入氡子体肺部有效剂量转换系数的影响因素研究

基于ICRP 66号报告中的呼吸道生物动力学模型,采用MATLAB软件中的Simulink仿真工具,建立了人体呼吸道的廓清模型,利用建立的廓清模型计算了不同参数条件下肺部有效剂量转换系数(mSv/WLM)的变化规律。结果显示吸入氡子体粒径对肺部有效剂量转换系数的影响最大,当粒径在0.7～10 000 nm之间变化时,肺部有效剂量转换系数的变化能达到10倍以上;其次是呼吸率,呼吸率直接决定了吸入氡子体粒子的数量,当成年男性重度工作状态时肺部有效剂量转换系数是睡眠状态下的4.2倍;未结合态份额对剂量转换系数的影响会随着吸入氡子体粒径值不同而发生改变,当未结合态份额从0变化到0.08时,肺部有效剂量转换系数最多能增大79%;相比而言吸收入血速率对肺部有效剂量转换系数的影响只有不到4%。     

水生生物体素模型的剂量转换因子计算

体素模型较以往的简化模型不仅在模型外形上更加贴近于实物,而且剂量率计算结果更具有说服力。本文以鲤鱼(体形规则)、河蟹(体形复杂)两种较为典型的水生生物为例,分别建立体素模型和简化模型,模拟计算水中137Cs源及90Sr对鲤鱼、河蟹不同器官(组织)的外照射与内照射剂量转换因子DCC,并对两种模型DCC值的差异性进行了分析及讨论,同时与欧共体非人类物种评价方法 ERICA及美国能源部非人类物种评价方法 RESRAD-BIOTA的DCC估算结果进行比对,结果都较为令人满意。     

根据小鼠卵母细胞存活率测得的氚β射线相对生物效应系数

选用11周龄,体重25—30克的 LACA 品系未经产雌性小鼠为实验动物。实验分为氚水内照射和~(60)Coγ射线外照射两部分。氚水是一次注入腹腔的,各照射组按每克体重计的注射量分别为4.7、17.0、37.0、75和110.0微居里,注射后10天内卵巢的累积剂量依次为3.9、141.、30、7、62.2和91.2拉德。~(60)Coγ射线外照射大致是模拟氚在卵巢内呈指数下降方式的剂量连续照射10天,每天照射22小时,10天内各照射组小鼠全身的累积剂量分别为52.6、77.18、108.22、161.87、194.25和269.88拉德。实验结果表明:当氚水内照射产生的卵巢累积剂量为3.9—62.2拉德、~(60)Coγ射线外照射产生的全身剂量为55—119拉德时,初级卵母细胞存活率呈指数下降。当卵巢的氚剂量为16拉德、初级卵母细胞存活率为20%时,氚的相对生物效应系数为2.28。     

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.     

Evaluation of radiation exposure upon visual organs during a head CT scan

In order to analyze and compare the absorbed radiation dose and dose rate of visual organs (eyes, corneas, and lenses) of the head with the surrounding areas of the head during CT scans, a mathematical head phantom was created. In addition, the amount of radiation exposure reduced when using an eye shield was also analyzed. According to the results, it was found that the absorbed dose was highest when using 120 kV (as compared to 80 kV and 100 kV) and the absorbed dose rate of the visual organs compared to the head was about 1.35% for the eyes, 0.9% for the corneas, and 0.095% for the lenses. Finally, it was shown that the dose reduction rate of each organ when using an eye shield was about 24% for the eyes, about 22% for the corneas, and more than 40% for the lenses.     

The effect of pitch and collimation on radiation dose in spiral CT

1 Introduction Spiral computed tomography (CT) was intro- duced in clinical practice in 1980s. Its distinctive characteristic is continuous data acquisition and con- tinuous tube rotation with high speed while simulta- neously translating the patient through the gantry.[1] Owing to these functions the spiral CT possesses the ability to scan an entire organ volume within a single breathhold. Thus, the anatomical section is contiguous and therefore the reliable demonstration of small le- sions…     

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.     

X(γ)刀吸收剂量测量方法研究

利用自制的直径f160mm有机玻璃球形模体和能够插入球形模体中心的PTW31006型0.015cm3尖点电离室测量了3种X(g)刀的等中心处不同辐射野的吸收剂量,并与半导体探测器(灵敏体积为1mm2?.5mm)的测量数据进行了比对,对电离室和半导体探测器的不同适用范围进行了分析,给出了一种适合X(g)刀的吸收剂量测量方法。     

10岁中国儿童参考人面元体模的建立

本文基于首都儿科研究所提供的中国儿童真实CT扫描图像建立了10岁中国儿童参考人面元体模。采用了多边形网格模型与NURBS曲面模型相结合的方法,建立了10岁中国儿童的多边形网格面元。体模包括85个器官,经过优化和调整,各组织和器官质量与GBZ/T 200 2-2007和亚洲参考人的参考值差异小于1%,各器官位置和形态符合中国儿童解剖学特征。该面元体模为10岁中国儿童剂量的准确计算提供了重要工具。     

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.     

Dose Conversion Coefficients for External Photons Based on ICRP 1990 Recommendations

Monte Carlo calculations were performed to estimate the effective doses E for external photons based on the recent proposals in the ICRP 1990 Recommendations. Twelve photon energies between 17 keV and 8.5 MeV and eleven irradiation geometries were selected to be applicable to many exposure conditions encountered in the working and living environment. A MIRD-based unisex phantom was used in conjunction with the Monte Carlo transport code MORSE-CG. The results were presented as a form of dose conversion coefficients transforming the air kerma or fluence in free air to the effective dose. These coefficients were given in graphical and tabular forms. Analyses of organs' fractional contribution to E showed that the gonadal exposure has generally a great contribution for all the geometries except the incidence from above. A comparison of conversion coefficients with other results gave a reasonably satisfactory agreement. Finally, the ambient dose equivalent H ^*(10), one of the operational quantities proposed by the ICRU, was found to give conservative estimates of E for most of the irradiation geometries considered, but it gives a considerable overestimate of E at the incidences from above and below.     

SPECT/CT活度定量中校准体模和重建方法的选择

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。     

TLD佩戴位置对估算外照射事故个人剂量的影响

本文报道了~(69)Co γ射线外照射个人剂量估算的体模实验结果,给出了不同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的比值(DROP),并对剂量计的几种佩戴位置进行了比较。