基于PCA和BM3D的噪声估计方法及其在中子图像去噪中的应用

针对中子图像的去噪问题,本文提出了一种弱化残差图像特征值的噪声估计方法。该方法将残差图像作为噪声图像,利用主成分分析（PCA）分析了残差图像特征值,估计了噪声强度。根据噪声强度,应用三维块匹配方法（BM3D）去除了噪声,逐步弱化残差图像特征值,得到了最终噪声估计值。实验结果表明,该方法能估计模拟噪声图像和实际含噪中子图像的高斯噪声,计算效率高,可实现较好的去噪复原效果。     

CT图像重建方法在半影成像中的应用

CT图像重建方法和半影成像是两种传统的辐射图像诊断方式。将CT图像重建方法应用到半影图像数据处理中,探索出一种新的半影图像处理方法。在新的半影编码孔图像数据处理中,首次应用了与图像诊断系统点扩散函数无关的编码孔图像处理方法,解决了传统编码孔图像处理中由于图像诊断系统点扩散函数不确定带来的技术难题。在理论研究的基础上进行了半影模拟成像及图像重建,获得了理想的研究结果。     

中子全息术中孪生像消除模拟

在中子全息照相的记录过程中,参考波与物波近似沿同一方向传播至全息屏,并在重建时形成不可分离的原像和共轭像,在特定波长下,两者可能干涉相消,产生孪生像现象。受制于中子探测效率和单色器能量分辨率,目前中子全息成像中孪生像的消除技术尚未得到系统的理论和实验研究。本文采用数值方法对已成功应用于X射线全息孪生像消除的两种全息记录及重建技术展开模拟,讨论基于研究堆的中子全息成像技术实现孪生像消除的可行性,并从实验效率和重建质量出发,对单色器分辨率、波数记录间隔、波数记录范围等关键参数进行定量分析和优化选取。结果表明,在研究堆中子源相对较低的单色器分辨率和较窄的可选能区条件下,通过记录2~4个不同能点的全息图即可获取较理想的中子全息重建结果。     

基于剪切波变换的辐射图像泊松噪声降噪技术研究

为了降低由统计涨落引起的辐射图像噪声，提出了一种基于剪切波变换的降噪方法。该方法以低剂量射线或质量厚度大的物体的辐射图像为研究对象，对此类辐射图像进行了噪声分析，利用Anscombe变换将统计涨落引起的泊松噪声转换为高斯噪声，再运用剪切波分解、阈值去噪、剪切波重构和Anscombe逆变换得到降噪图像。结果表明，当剪切波分解层数为5，采用改进阈值函数及极小极大原理阈值时可达到最优降噪效果，该方法能较好地去除辐射图像中的泊松噪声并保留边缘、细节信息，在视觉和量化指标上均优于传统降噪方法。     

Element analysis method of concealed explosive based on TNA

The detection technology of concealed bulk explosives is related to social security and national defense construction and has important research significance. In this paper, an element analysis method of concealed explosives based on thermal neutron analysis is proposed.This method could provide better reconstruction precision for hydrogen, carbon, and nitrogen ratios, making it possible to discriminate explosives from other compounds with the same elements but different proportions, as well as to identify the types of concealed bulk explosives. In this paper, the basic principles and mathematical model of this method are first introduced, and the calculation formula of the element number ratio(the ratio between the nucleus numbers of two different elements) of the concealed explosive is deduced. Second, a numerical simulation platform of this method was established based on the Monte Carlo JMCT code. By calibrating the absorption efficiencies of the explosive device to c rays, the element number ratios of a concealed explosive model under the irradiation of thermal neutrons were reconstructed from the neutron capture prompt c-ray spectrum. The reconstruction values were in good agreement with the actual values,which shows that this method has a high reconstruction precision of the element number ratio for concealed explosives. Lastly, it was demonstrated using the simulation study that this method can discriminate explosives,drugs, and common materials, with the capability of determining the existence of concealed bulk explosives and identifying explosive types.     

基于模极大值法的γ能谱数据处理与分析

本文研究了Lipschitz指数与小波变换应用于γ能谱数据奇异点的使用方法,分析了模极大值去噪原理和Mallat提出的交替投影重构算法,建立了基于模极大值法γ能谱数据处理模型,基于MATLAB设计了小波变换模极大值去噪软件,通过实测γ能谱数据仿真分析基于模极大值法的γ能谱数据处理模型的效果。结果表明,利用小波变换模极大值法降噪,用交替投影法重构能谱数据,降噪效果较好。     

形态滤波在快中子图像降噪处理中的应用

在基于CCD耦合闪烁光纤阵列的快中子照相系统中,快中子图像受噪声污染较为严重.针对快中子图像中的椒盐噪声和泊松噪声,研究了形态滤波技术在降噪方面的应用.结果表明在对快中子图像处理过程中,基于二维多方向结构元素的形态滤波在滤除噪声和保持图像细节等方面效果较佳.     

The pseudo-harmonics perturbation method: Application to a PWR

A modified version of the pseudo-harmonics method for perturbed neutron flux reconstruction is described together with a number of applications relevant to a PWR-type nuclear reactor, with three enrichment zones and with material constants representative of those of the ANGRA-I power plant. Global and localized perturbations were simulated. The eigenvalue convergence criterion showed that only a few orders of approximation were needed to calculate the neutron flux alterations, indicating the potentiality of the method investigated. The number of pseudo-harmonics used depended in each case on the type and intensity of the perturbation considered.     

核乳胶中质子径迹计算机辅助识别方法研究

为克服核乳胶质子径迹人工判读的缺点,研究了一种计算机辅助识别的方法。该方法中,对由显微镜系统获取的核乳胶图像序列依次经组合式滤波器滤波、多阈值二值化、径迹点筛选、径迹点去冗余处理后识别出图像序列中的径迹点,经径迹重建从获取的径迹点中重建出反冲质子径迹。利用该方法从经14.9 MeV中子束辐照的核乳胶中提取出反冲质子径迹,并将提取的径迹与人工判读方法提取的径迹进行了比较,结果基本一致。该方法将为核乳胶质子径迹自动判读系统的开发和核乳胶应用于脉冲中子束能谱测量实验奠定重要技术基础。     

An algorithm for ~(252)Cf-Source-Driven neutron signal denoising based on Compressive Sensing

As photoelectrically detected ~(252)Cf-source-driven neutron signals always contain noise, a denoising algorithm is proposed based on compressive sensing for the noised neutron signal. In the algorithm, Empirical Mode Decomposition(EMD) is applied to decompose the noised neutron signal and then find out the noised Intrinsic Mode Function(IMF) automatically. Thus, we only need to use the basis pursuit denoising(BPDN) algorithm to denoise these IMFs. For this reason, the proposed algorithm can be called EMDCSDN(Empirical Mode Decomposition Compressive Sensing Denoising). In addition, five indicators are employed to evaluate the denoising effect. The results show that the EMDCSDN algorithm is more effective than the other denoising algorithms including BPDN. This study provides a new approach for signal denoising at the front-end.     

基于小波变换的Wiener滤波投影预处理算法在图像重建中的应用

研究了一种将小波变换与Wiener滤波相结合用于投影数据预处理的算法。由于小波变换具有多分辨率分析特性,通过小波多尺度分析和小波系数控制,并结合Wiener滤波具有MMSE上最优性能的特点提出一种二者相结合的方法用于投影数据降噪预处理。对该算法进行实验仿真,结果表明,降噪后重建的图像主观质量得到明显改善,重建图像的噪声得到有效抑制。峰值信噪比方面可比一般的降噪方法提高5-12dB。     

Simulation and Performance Study on Compact Thermal Neutron Collimator Based on Gadolinium doped Silicate

In order to achieve the goal of nuclear security, the neutron generator is used to image shielded nuclear material by non-destructive analysis method. In order to improve the imaging quality, it is necessary to collimate the slowed neutrons. In this paper, the Monte Carlo software Geant4 was used to theoretically model a new compact thermal neutron collimator based on gadolinium-doped silicate, and the thermal neutron transmittance and collimation ratio of the collimator were simulated and calculated. The calculation results will be used to guide the subsequent construction of neutron-based nuclear material imaging systems.     

基于硅酸盐钆掺杂的紧凑热中子准直器仿真模拟及性能研究

在核安保管理中,基于中子发生器的热中子成像技术可对被屏蔽核材料进行无损检测成像。为提高成像质量,需对慢化后的中子进行准直。本文使用蒙特卡罗软件Geant4对一种基于硅酸盐钆掺杂的紧凑中子准直器进行了理论建模,对该准直器的热中子透过率和准直率进行了模拟计算,计算结果将用于指导后续的核材料中子成像系统构建。     

基于中子IP板的核燃料元件间接中子CT实验方法研究

中子照相作为一种无损检测技术是分析和确定核燃料元件缺陷的重要手段。中国原子能科学研究院中子照相团队依托中国先进研究堆（CARR）中子照相测试平台,搭建了核燃料元件间接中子CT装置,并开展核燃料元件模拟件的间接三维中子成像技术研究。本文首先采用蒙特卡罗模拟方法优化确定了样品环境转移屏蔽容器的关键参数并研制出屏蔽容器,并基于该装置开展了核燃料元件模拟件的间接中子CT照相实验,从获得的三维实验数据可观测到尺寸约0.35 mm模拟芯块缺陷。实验结果表明,该装置可满足核燃料元件的间接中子CT实验检测。同时初步研究了基于IP板的间接中子成像数据处理的制约因素和方法,为后续进一步利用金属转换屏替代中子IP板等技术,真正实现乏燃料元件无损检测应用提供实验指导。     

新型耐高温中子屏蔽复合材料的设计制备及性能研究

采用表面改性处理技术,制备了由环氧树脂、B₄C（或BN）和聚丙烯酸铅组成的新型耐高温中子屏蔽复合材料,重点研究了材料制备工艺及主要性能指标,利用蒙特卡罗程序MCNP对材料中子屏蔽性能进行了模拟计算,并与文献报道的屏蔽材料铅硼聚乙烯进行了比较。结果显示,由环氧树脂、B₄C和聚丙烯酸铅组成的复合材料各项力学性能良好,具有良好的耐高温性能,210 ℃烘烤7 h外观无明显变化。MCNP模拟计算表明,对于从热中子至10 MeV的中子,4 cm厚新材料的中子剂量穿透率和中子注量穿透率均优于文献报道的同等厚度的铅硼聚乙烯材料。Am-Be中子源屏蔽试验的实测数据和模拟计算数据表明,两者随屏蔽材料厚度的变化趋势几乎完全一致,两者的差异随屏蔽材料厚度的增加逐渐减小,在10.5 cm处仅1.34%。     

用中子活化分析镀膜厚度及其探测极限研究

本工作提出用中子活化分析有基底的单层或多层镀膜厚度的方法。用Am-Be中子源对Au、Al、Cu等薄膜活化后,用HPGe探测器测量被活化薄膜放出的特征γ射线全能峰面积,并用蒙特卡罗方法模拟计算HPGe探测器对不同特征γ射线的探测效率,得到用反应堆中子源活化分析不同元素镀膜厚度的方法和探测极限。与目前广泛使用的X射线荧光方法相比,其分析灵敏度可提高几个量级。     

基于模拟点源测量的多针孔SPECT精确迭代重建

高分辨率单光子发射计算机断层成像（SPECT）是临床和小动物影像的重要技术之一。对SPECT的系统传输矩阵进行建模,并结合于迭代重建算法中,是提高系统空间分辨率的有效手段。本文基于实验室自主研发的多针孔小动物SPECT系统,研究了一种蒙特卡罗模拟和解析模型相结合的系统传输矩阵精确计算方法。该方法是基于多点源模拟的投影数据,结合数据再估计方法和高斯拟合方法提取点扩展函数（PSF）特征参数,并结合解析形式的系统物理模型,从而计算任意位置的精确PSF。通过对四点源模拟投影数据分别用纯解析方法和蒙特卡罗模拟与解析模型相结合的方法进行计算,并对所得的系统传输矩阵进行重建对比,验证了蒙特卡罗模拟与解析模型相结合方法对图像分辨率的改善效果。进一步比较了不同点源排列的重建效果,获得了优化的点源排布方案。相对于基于实验方法测量系统传输矩阵,本方法能以更合理的代价实现系统传输矩阵的精确建模,并能有效提高系统空间分辨率。     

基于调制核回归和正则化Richardson-Lucy算法的中子图像复原方法

由于中子成像系统中的诸多物理因素影响,使其得到的中子图像通常会发生严重的图像降质。本文将调制核回归(SK)引入到TV-RL算法中,提出了一种中子图像去模糊去噪方法 SK-TV-RL,即基于SK的TV-RL算法。该方法能解决以往算法噪声放大的问题,并能复原降质图像中的细节信息。对比实验结果表明,无论基于客观评价还是主观评价,该方法都能有效地提高图像复原质量。     

Point Scattered Function (PScF) for fast neutron radiography

Fast neutron radiography opened up a new range of possibilities to image extremely dense objects. The removal of the scattering effect is one of the most challenging problems in neutron imaging. Neutron scattering in fast neutron radiography did not receive much attention compared with X-ray and thermal neutron radiography. The purpose of this work is to investigate the behavior of the Point Scattered Function (PScF) as applied in fast neutron radiography.The PScF was calculated using MCNP as a spatial distribution of scattered neutrons over the detector surface for one emitting source element. Armament and explosives materials, namely, Rifle steel, brass, aluminum and trinitrotoluene (TNT) were simulated. Effect of various sample thickness and sample-to-detector distance were considered. Simulated sample geometries included a slab with varying thickness, a sphere with varying radii, and a cylinder with varying base radii. Different neutron sources, namely, Cf-252, DT as well as DD neutron sources were considered. Neutron beams with zero degree divergence angle; and beams with varying angles related to the normal to the source plane were simulated.Curve fitting of the obtained PScF, in the form of Gaussian function, were given to be used in future work using image restoration codes. Analytical representation of the height as well as the Full Width at Half Maximum (FWHM) of the obtained Gaussian functions eliminates the need to calculate the PScF for sample parameters that were not investigated in this study.     

基于BM3D frames和方差稳定化变换的中子图像复原方法

中子照相是无损检测中应用较为广泛的一种技术。然而中子成像系统诸多不可避免的物理因素会导致所得中子图像严重降质,如噪声污染和空间模糊等。针对此问题,本文提出了一种将BM3D frames和方差稳定化变换相结合的中子图像复原方法。此方法首先对图像中的泊松高斯噪声进行变换,变换后数据成为符合高斯分布的噪声,然后用BM3D frames滤除变换后的高斯噪声,最后对去噪结果进行逆变换即得复原图像。该方法对强泊松高斯噪声有很强的抑制作用,且可很好地保留降质中子图像中的细节。实验结果表明,该方法在客观数据和视觉感受上均表现出稳健高质的复原性能。