Effects of internal scattering on X-ray microtomography imagereconstruction

A computer simulation is used to study the problem of internal scattering for targets that are imaged using X-ray microtomography. A strategy is outlined for selecting X-ray energy and image resolution based on properties of the material being imaged. The X-ray scanning process is simulated by applying a Monte Carlo technique to a modeled target that emulates the material properties of a microelectronic device. The X-ray photons are subject to photoelectric absorption, Rayleigh scattering, and Compton scattering. The simulation applies a method of high-resolution image reconstruction based on discrete Fourier transforms. Examples of reconstructed images that have 0.5-μm spatial resolution are shown for images of simulated lead and aluminum targets     

中子共振谱在爆炸危险品精确探测中的应用

在车站、港口和机场对行包中可能夹藏的易燃易爆等危险物品的检查,通常是借助X射线进行的,但X射线技术主要是根据物质密度不同进行探测,对爆炸危险品的探测效果不够理想.中子共振谱则只和元素密切相关,因此利用中子共振谱技术可以准确地判定物质中各元素的准确含量.各种爆炸危险品的主要成分C、H、N、O等元素在0.5～7.5MeV能量区间具有显著的中子共振谱特征,利用该区间各共振峰的中子吸收截面差异构建的多元一次方程组,可以得到C、H、N、O等元素在物质中的精确含量比,从而达到直接判定待测物质种类的目的.中子共振探测技术可以充分应用在国防、民用安全检测和防恐等领域中,具有良好的实用前景.     

强脉冲X射线辐照含间隙多层材料动力学效应的SPH模拟

脉冲X射线辐照材料时,会在材料中形成能量沉积并产生热击波。目前一般使用差分法对所形成的热击波进行数值模拟,但若考虑多层材料之间的间隙,差分法处理起来比较困难。本文使用SPH方法对脉冲X射线辐照含间隙多层材料进行了数值模拟。结果表明,各层材料之间的缝隙对热击波的强度具有一定的影响,而对表面气化反冲冲量没有影响。     

电子束与复合靶作用后辐射特性的数值模拟

建立了复合靶的蒙特卡罗粒子输运计算模型,以“闪光二号”加速器为电子束源,模拟了电子和光子在不同材料中的输运规律,研究了钽和聚乙烯组成的复合阳极靶对辐射X射线场的影响。模拟结果表明：随着钽厚度的增加,辐射X射线平均能量增大,能量转换效率先增大后减小;聚乙烯可明显减小辐射场中的电子份额。当钽和聚乙烯的厚度分别取20 μm、3 mm时,辐射场中平均光子能量为102.68 keV;光子总能量为88.62 J,远大于电子总能量0.02 J;X射线能量转换效率为0.57%。根据数值模拟结果和实验条件设计了复合靶,计算和测得的X射线平均能量分别为108和121 keV,二者符合得较好。     

Computed tomography reconstruction from two transmission measurements for iodine-marked cancer detection

The authors invented the transXend detector, which measures X-rays as electric currents, and then gives the energy distribution of the X-rays after an unfolding process. In a previous paper, it was shown that the material thickness distributions can be estimated with the transXend detector by using reference points plotted from the electric current ratios, such as the I ₂/I ₁ ? I ₃/I ₁ graph, where I_i denotes the electric current measured by the i-th segment of the transXend detector. In this paper, the tomographic images of iodine, aluminum, and the acrylic those surround the other two materials are reconstructed from their material thickness distributions, which are estimated from two X-ray incidence directions. The X-ray event ratios are also used to estimate the material thickness distributions.     

Novel methodology for the quantitative assay of fissile materials using temporal and spectral β-delayed γ-ray signatures

An analytical model for the generation of β-delayed γ-ray spectra following thermal-neutron-induced fission of mixed samples of ²³⁵U and ²³⁹Pu is presented. Using an energy-dependent figure-of-merit to designate the spectral regions employed in the assay, the unique temporal β-delayed γ-ray signatures are utilized to determine the fraction of ²³⁹Pu in a mixed U-Pu sample. By evaluating the β-delayed γ-ray temporal signatures of both ²³⁵U and ²³⁹Pu within a 3 keV energy bin, traditional sources of systematic uncertainty in quantitative assay using β-delayed γ-ray signals, such as self-attenuation of the sample and energy-dependent γ-ray detection efficiency, are significantly reduced. The effects of the time-dependent Compton-continuum and growth of longer-lived nuclides on the quantitative assessment are explored. This methodology represents a promising extension of the conventional means of analysis for quantitative assay of fissile materials using β-delayed γ-ray signatures.     

Calculation of photon shielding properties for some neutron shielding materials

The objective of the present study is to calculate photon shielding parameters for seven polyethylene-based neutron shielding materials. The parameters include the effective atomic number(Z_(eff)), the effective electron density(N_(eff)) for photon interaction and photon energy absorption,and gamma-ray kerma coefficient(kc). The calculations of Z_(eff)are presented as a single-valued and are energy dependent. While Z_(eff)values were calculated via simplistic powerlaw method, the energy-dependent Z_(eff)for photon interaction(Z_(PI-eff)) and photon energy absorption(Z_(PEA-eff)) are obtained via the direct method for energy ranges of 1 keV–100 GeV and 1 keV–20 Me V, respectively. The kccoefficients are calculated by summing the contributions of the major partial photon interactions for energy range of 1 keV–100 MeV. In most cases, data are presented relative to pure polyethylene to allow direct comparison over a range of energy. The results show that combination of polyethylene with other elements such as lithium and aluminum leads to neutron shielding material with more ability to absorb neutron and crays. Also, the kerma coefficient first increases with Z of the additive element at low photon energies and then converges with pure polyethylene at energies greater than 100 keV.     

Numerical simulation of high-energy neutron radiation effect of scintillation fiber

Due to their low cost,flexibility,and convenience for long distance data transfer,plastic scintillation fibers (PSF) have been increasingly used in building detectors or sensors for detecting various radiations and imaging.In this paper,GEANT4 Monte Carlo simulation tool was used to obtain some radiation effects of PSF under high-energy neutron irradiation.BCF-20,a plastic fiber material,produced by Saint-Gobain,was used in the simulation.The fiber consists of a core scintillating material of polystyrene and an acrylic outer cladding.Incident neutrons produce energy deposition in fiber through neutron induced recoil proton events.The relationships between energy deposition efficiency and fiber length,fiber radius and incident neutron energy are presented.The variation with those parameters and parameter selection are also analyzed.     

Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code

In this paper,mass attenuation coefficients of concrete,bricks and cement plaster,as shielding materials,are calculated at 59.5,356,662,1173,1274 and 1333 keV by using the MCNP-X (version 2.4.0) code.The numerical simulation results are compared with previous Monte Carlo studies,experimental results and XCOM data.The effects of barite on mass attenuation coefficients are investigated.The mass attenuation coefficients increase with the barite content.Thus,our results agree well with experimental studies on gamma ray shielding of barite.It is flexible for the MN method to change the barite rates in material by small increments,which is experimentally difficult.Also,modeled geometry can be used for future approaches such as new designs and new structures especially in investigating new barite-containing materials to build nuclear reactors or high-energy radiation therapy facilities.     

基于能谱等效的合金补偿方法研究

针对连续能谱X射线厚度测量中的合金补偿问题,利用能谱等效思想,根据单能射线下合金补偿系数与射线能量之间及连续能谱射线下合金补偿系数与材料厚度之间均存在单值对应关系,以合金补偿系数为参考,将连续能谱射线下的合金补偿问题转化为单能射线下的合金补偿问题。提出了系统标定、厚度标定、单能标定及能量等效的具体方案。利用蒙特卡罗程序建立了适用于X射线厚度测量的仿真模型,对能谱等效结果进行了验证。结果表明,30种不锈钢材料板按能谱等效结果进行合金补偿后,厚度测量相对误差90%以上小于0.1%,表明基于能谱等效思想的合金补偿方法可行性高、适用性广。该方法中的能谱等效结果对连续能谱射线硬化研究有参考意义。     

Magnetic Susceptibility of Uranium Carbonitride

The possibility of analyzing the integral data obtained by fast critical experiments in the two-mode framework was investigated by numerical experiments. Nuclear model is 26-group zero-dimensional one, maintaining criticality by energy-independent geometrical buckling. Two energy modes used in this paper were chosen by observing the distribution of fundamental spectra of various assemblies on the reaction-rate space. By synthesizing these two modes, we can evaluate the eigenvalues of various dilute fast assemblies with the maximum error 0.7%.

By the investigations, following conclusions were obtained. The modal combining coefficients can be estimated by measuring the spectral index, and the suitable combination of reactions for this purpose is the set va _f of ²³⁸U/vσf; of ²³⁵U. The coefficients of importance spectra can be evaluated by measuring the material worth, on the basis of the first-order perturbation theory. Unknown mode-constants and adjoint-weighted mode-constants can be determined by measuring spectral indicies and material worths, respectively, in various assemblies where the modal combining coefficients were determined in advance. The errors in the spectral indicies and the material worths which are calculated by using these estimated mode-constants are less than a few percent and some 10%, respectively.     

Development of precise energy spectrum measurement technique for high-power pulsed X-ray sources for industrial use

It is difficult to obtain an accurate energy spectrum by measurement for X-rays which are produced by linear accelerators because so many photons are emitted within a very short period and the photons have energies in a wide range. In order to solve the problem, we developed a new technique utilizing the Bayesian estimation method combined with attenuation curve measurement using a step-shaped attenuation material. We experimentally confirmed the validity of the presented technique for an X-ray computed tomography (CT) system. By using the accurate energy information of emitted X-rays obtained by the developed technique, the quality of non-destructive inspection images can be expected to be improved for industrial X-ray radiography, X-ray CT and so on, using high-power X-ray sources.     

Peak shape methods for general order thermoluminescence glow-peaks: A reappraisal

This paper presents a reappraisal of the well known peak shape expressions for calculating the activation energy E in a thermoluminescence (TL) glow-peak. This study leads to new insights as to the meaning of the coefficients used in the original equations. The reappraisal leads to new equations for the coefficients of the peak shape expressions which contain the general order parameter b, instead of the experimentally determined geometrical shape factor which is used in the original equations. Previously only the coefficients for first and second order kinetics were determined on the basis of existing theory and the coefficients for intermediate kinetics order were determined empirically using a linear interpolation-extrapolation method. In the present work the improved peak shape coefficients are evaluated in analytical form as a function of the kinetic order b, by using the general order kinetics expression for the TL intensity. The intrinsic errors in the newly derived expressions for E are evaluated and their relevance to experimental work is discussed in detail. A method for a further improvement of the accuracy of the peak shape methods is suggested.     

不同带电情况下介质材料二次电子发射特性研究

空间材料二次电子发射特性是决定航天器表面带电速率和充电平衡电位水平的重要参数。本文利用1~5keV的脉冲电子束开展了聚酰亚胺(kapton)、玻璃盖片和光学太阳反射镜(OSR)材料的二次电子发射系数(δ)测试,并完成了介质材料表面不同充电情况下的二次电子发射特性研究。研究结果表明,在入射电子能量为1~5keV范围内材料二次电子发射系数随入射电子能量上升而下降,同时当二次电子发射系数大于1时,材料表面将累积正电荷,二次电子发射系数下降,当二次电子发射系数小于1时,材料表面将累积负电荷,二次电子发射系数将增加。     

Mass thickness measurements for dual-component samples utilizing equivalent energy of X-rays

In this paper,equivalent energy method is introduced for measuring mass thickness of dual-component samples using dual-energy X-rays.Approximately,the method adopts equivalent mass attenuation coefficients of the two components in mass thickness measurements for dual-component samples,in a certain range of thicknesses.Feasibility of the method is proven by numerical calculations and Monte Carlo simulations（EGSnrc package）.The results of absorption experiments using an X-ray machine at tube voltages of 30 and 45 kV,the relative errors are less than 5%between the nominal and detected values.Also,optical low energy is discussed at given high voltages.     

A Comparison of Various Filter and Discriminator Techniques on Timing with Ge(Li) Detectors

An experimental examination of the effect of several filters and two discriminator techniques on the time measurement of the signals from coaxial Ge(Li) detectors is presented in this paper. The signal to the filters and discriminators was obtained from the output of the charge-sensitive preamplifier in order not to degrade the energy resolution of the system. The discriminators used were a level discriminator for leading-edge discrimination and a fast zero-crossing discriminator. The filters examined for leading-edge discrimination were four RC time-invariant and four RC time-variant filters, and the filters for zero-crossing discrimination were three time-invariant RC filters. A comparison of time-invariant and time-variant filters reveals two advantages of the time-variant filter. These advantages are smaller timing errors and lower discrimination levels. The lower discrimination levels allow the reduction of energy dependent timing errors. Likewise, zero-crossing discrimination provides several improvements over leading-edge discrimination. By a compensation method, timing errors due to charge collection variations are reduced; and, due to the invariancy of the zero-crossing point as a function of amplitude, energy-dependent timing errors are also reduced.     

Simulating nuclear particle transport in stochastic media using Perlin noise functions

Many nuclear particle transport problems require the simulation of stochastic media – that is, media whose composition varies randomly as a function of position. Examples include biological tissues, mineral slurries and crushed mineral ores. Such materials are usually represented in particle transport codes as being homogeneous with an appropriate average composition. This approximation can introduce significant errors.A new method is described for simulating the transport of neutral particles in such media using a three-dimensional Perlin noise function [Comput. Graph. 19 (3) (1985) 287]. The technique allows many properties of the stochastic medium to be specified, including the mean scale of the inhomogeneities, their shape and surface roughness and the proportions of the different media making up the stochastic medium. A key property of the new method is that the tracking speed is independent of the number density of the inhomogeneities.The tracking algorithm has been implemented into the EGSnrc [The EGSnrc code system: Monte Carlo simulation of electron and photon transport, NRCC Report PIRS-701, 2000] Monte Carlo code. An example application is described, modelling X-ray fluorescence from a particulate mineral sample. In contrast to the homogeneous approximation, the new algorithm accurately reproduces the observed particle size dependence seen experimentally. The increase in computational time is fairly modest, even for very small particle sizes.     

MC法计算γ射线外照射剂量转换因子

以剂量转换数学模型为基础,针对骨、软组织和水的等效组织球体剂量计算,采用蒙特卡罗软件MCNP5构建0.01~10 MeV的γ射线在这三种物质中的通量和能量沉积模拟模型,进而计算这三种物质的γ外照射剂量转换因子。同时给出这三种物质的γ外照射剂量转换因子对不同能量γ光子的拟合计算公式,并进行了数据验证。结果表明:剂量转换因子在γ射线能量低于0.15 MeV时,随着能量的增加按幂函数降低;高于0.15 MeV时,按指数函数上升;剂量转换因子模拟值与参考值随γ射线能量的变化规律相同。     

Molecular dynamics simulation of low energy cluster impacts on carbon nanotubes

The controlled doping of carbon nanotubes is of much interest in the production of potential new nanometer scale devices. Selective doping has been achieved for many years in the silicon microelectronics industry using ion implantation as it is highly controllable. However, with nanostructures and in particular the use of carbon nanotubes the impact energy delivered with the dopant ion in conventional ion implantation is distributed to the target material in such a way that substantial damage of the structure ensues.Recently Yamada et al. have been employing large gas cluster beams at relatively low energy per atomic particle so that the target material does not undergo such direct kinetic energy transfer. This relatively new technique – known as infusion doping in silicon technology – suggests a new, less damaging, technique for introducing dopants into nanostructured materials. Here we make an initial simulation study of the impact of a large gas cluster, containing a fraction of dopant ions, onto a single wall nanotube to investigate the possible doping and survival rate of this mechanism over the more conventional single atomic ion implantation technology.     

蒙特卡罗模拟确定γ射线衰减系数函数及参数

在中低密度样品中,γ射线的线衰减系数主要由γ射线能量和样品密度决定,采用MCNP(Monte Carlo N Particle Transport Code)程序模拟计算了多种γ射线能量和多种样品密度条件下的线衰减系数,对线衰减系数模拟值进行多元非线性回归,确定了以γ射线能量和样品密度为因变量的线衰减系数函数及参数。实验测定了三种能量γ射线在6种不同密度样品中的线衰减系数值,并与模拟所得函数值进行比较分析。结果表明,所得函数值与实验值的相对误差均在7%以内,蒙特卡罗程序计算所得函数值与实验测量值较为吻合,所采用的函数模型准确验证了线衰减系数与γ射线能量、样品密度之间的关系特征。