大型工业螺旋CT的多平面重组及交互可视化处理技术

大型工业CT是检测大型火箭和导弹的重要手段，在需要了解被检部位上下关系时，需要对获得的断层图像进行多平面重组，并应用交互可视化技术，在计算机上获得空间图形或任意平面的图像，讨论了各种多平面重组的方法及其特性，描述了如何在Windows环境下用OpenGL实现三维交互可视化，并给出了一个简单的三维交互可视化程序和结果。     

MATLAB编程实现连续断层工业CT图像的三维重建

工业CT图像的三维重建是无损检测领域的重要组成部分.应用MATLAB编程,对连续多层工业CT图像进行了三维重建,获得了具有较好立体感显示的三维图像,通过对三维图像的剖切、透明等显示,可以观察到物体的内部结构,得到了更直观和丰富的物体检测信息.     

伪彩色数字高程模型在工业CT断层图像检查中的应用

在工业CT断层图像缺陷检测应用中，提出了将数字高程模型DEM与伪彩色技术一起应用于二维灰度图像缺陷检测领域的算法流程。应用该算法流程，能够充分利用CT断层灰度图像信息，获得清晰的视觉检查效果，从而大大增强了系统检测缺陷的能力。在大型工业CT图像重建与检查分系统中采用该算法流程已经取得了较为理想的效果。     

基于Wintel和P4架构的大型工业CT图像快速重建实现研究

探讨了实现大型工业CT图像快速重建检查的可行性以及后续展望。这对于降低大型工业CT的开发和应用成本，提高工业CT产品的性价比具有重要的意义。     

二维直方图阈值法分割工业CT图像的研究

高精度工业CT图像因其包含物体三维信息而被广泛重视。尤其对于某些工件的缺陷检测，可利用图像分割技术进一步识别、突显缺陷，提高检测效率。针对一类工件的缺陷，对其高精度CT图像先后采用了比特窗算法进行预处理和二维直方图阈值法进行分割，突出显示了该类缺陷。该类方法对类似问题有广泛应用。     

三维重建技术在工业CT中的应用

用图像的三维重建技术,实现连续断层CT图像的三维可视化是近年来国内工业CT领域内的-个重要研究方向.用三角面片连接轮廓线方法,实现了连续等间隔工业CT图像的三维重建,获得了扫描物体的三维立体显示图像.通过计算机交互操作,实现多角度、多方位观察物体,无损测量物体三维参数等功能.利用重建出的三维图像,检测人员可以获得物体更多的空间结构信息,从而提高无损检测的方便性和准确性.     

工业CT图像的三维重建

工业CT图像三维重建是近年来工业CT技术研究的热点之一,将二维断层图像数据直接堆垒起来,结合阈值分割、线性内插等方法,获得了直观性较好的三维工业CT图像。通过对重建图像进行旋转、截取等操作,获得了不同方向、不同部位的三维图形。这种简单、快速的重建方法对更复杂的工业CT图像三维重建具有重要的指导意义。     

三维可视化在60Co集装箱CT检测系统中的设计与实现

本文设计实现了一种三维可视化系统,针对60Co集装箱CT检测系统的数据采集、CT图像重建等过程特点,采用了Ray Casting体绘制的三维显示模式.其绘制子系统不影响CT检测系统在研发过程中其它子系统的改进,方便了各子系统功能的完善与扩展.此三维可视化系统在60Co集装箱CT检测系统中的实验效果较好,可以辅助安检人员...     

大型工业CT流水线图像重建

大型工业CT中，采用等角度扇形束扫描，为达到高分辨率，需要在每个投影下微动探测器。多次采集数据。为了节省成像时间，设想让重建计算和数据采集同时进行，称为流水线图像重建法。研究了这种 水线图像重建方法，并与传统方法的效率进行了比较。     

CT局部重建算法发展综述

主要研究CT图像重建领域中的局部重建算法，介绍了最近十几年来局部重建算法的发展过程、目前的发展情况，以及局部重建算法的研究方向；重点介绍了几种通用的局部重建算法并对它们的重建结果进行了对比分析，最后对局部重建算法在工业CT领域中的应用进行了分析和介绍并对局部重建的发展进行了展望。     

三维可视化技术在矿产资源勘探领域中的应用探讨

地质体三维可视化技术的研究是“数字勘探”领域的重要组成部分，本文针对矿产资源勘探数据的特点，研究了适合地质体信息三维可视化的体素模型和空间插值算法。基于交互式数据语言(IDL)，开发了三维数据可视化软件；该软件能够快速、准确地将地质体的空间展布形态以及物性特征展示出来。     

数字化平均流强测量方法研究

平均流强测量可用DCCT或ICT探头,ICT探头有很强的抗电磁干扰能力,但测量精度不高.用高精度A/D转换器和等效采样测量算法使ICT探头组成的平均流强测量系统有较高的测量精度.本文主要介绍了基于ICT探头的平均流强测量系统、测量算法和实验室测试结果.     

大型工业CT中X射线硬化校正的一种方案

介绍了大型工业CT的一种多色X射线硬化校正方法。该方法利用一个标准函数将多色投影值转化为单色投影值。定义了一些参数来证明该方法适用于大型工业CT的硬化校正,并对参数进行了优化。通过模拟实验,这种校正方法在不需要先验知识,使用单色重建算法的前提下,仍能大大减小CT重建图像的硬化伪像。     

面向对象仿真技术在大型集装箱检查系统R&D中的应用

介绍大型集装箱检查系统中的计算机仿真软件ECS及其开发的过程和方法;论述在大型集装箱检查系统中所使用的面向对象模拟仿真技术;总结面向对象方法仿真方法仿真在大型核技术设备研发中的特点和优势。     

基于卷积神经网络的大尺寸气泡体积二维图像测定方法

由于表面张力与惯性力作用,静止流场内较大尺寸气泡[500<气泡雷诺数（Re）<2000]形成不规则几何形状,造成二维图形处理方法等效球体或椭球获取三维体积的方式误差较大。此外,由于不规则界面的散射和反射,引起二维图像处理中边界模糊,难以辨识。本文以高速摄像机获得的静止流场内大尺寸气泡二维灰度图像作为卷积神经网络（CNN）的输入,以图像内气泡二维投影面积及实验获得三维体积训练网络,并用训练好的网络预测气泡体积。实验采用小气泡叠加法获得真实气泡体积,与网络预测结果进行对比。结果表明,该方法与传统图像处理方法相比,不需要对气泡形状进行假设,提高了对大尺寸气泡的适用性。      

Equivalent circuit model for the insulated core transformer

The design of the insulated core transformer(ICT)needs to consider the flux leakage effects.An equivalent linear circuit model is proposed based on the principle of duality.It is composed by two types of leakage inductances:conventional leakage between windings and special leakage introduced mainly by the insulation gaps.The values of leakage inductances depend on the dimensions of the core,gaps,or windings and the property of magnetic materials.The circuit allows for quantitatively evaluating influences of ICT internal parameters on its output properties.The winding self- and mutual inductance matrix is mathematically converted to derive the inductance formula.As an example,the leakage parameters of a sixstage two-dimensional(2D) ICT are calculated and analyzed.     

Neutronic design of hydride fueled BWRs

This paper summarizes the neutronic part of a study of the feasibility of designing BWR cores to have enhanced power density and simplified fuel bundle by using hydride instead of oxide fuel. A 3D fuel bundle neutronic analysis is performed for a limited number of geometries to determine attainable discharge burnup, pin-by-pin power distribution, axial power distribution, reactivity coefficients, reactivity worth of control elements and burnable absorber effects. It is found that hydride fuel bundle design can be simplified by eliminating water rods and partial length fuel rods and by reducing the volume of water in-between the fuel bundles. Both an ideal and more practical bundle designs are examined. A companion study of the thermal-hydraulic and vibration characteristics of BWR cores predicts that the increase in the number of fuel rods per given core volume enables increasing the BWR power density by up to ∼30% relative to oxide fuelled core design. The net outcome is expected to be improved BWR economics even though hydride fuel requires higher uranium enrichment to compensate for its reduced uranium loading.     

Synergism of the method of characteristic, R-functions and diffusion solution for accurate representation of 3D neutron interactions in research reactors using the AGENT code system

This paper summarizes the theoretical and numerical aspects of the AGENT code methodology accurately applied for detailed three-dimensional (3D) multigroup steady-state modeling of neutron interactions in complex heterogeneous reactor domains. For the first time we show the fine-mesh neutron scalar flux distribution in Purdue research reactor (that was built over forty years ago).     

Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models

In the framework of joint effort between the Nuclear Energy Agency (NEA) of OECD, the United States Department of Energy (US DOE), and the Commissariat a l'Enerige Atomique (CEA), France a coupled three-dimensional (3D) thermal-hydraulics/neutron kinetics benchmark was defined. The overall objective of OECD/NEA V1000CT benchmark is to assess computer codes used in analysis of VVER-1000 reactivity transients where mixing phenomena (mass flow and temperature) in the reactor pressure vessel are complex. Original data from the Kozloduy-6 Nuclear Power Plant are available for the validation of computer codes: one experiment of pump start-up (V1000CT-1) and one experiment of steam generator isolation (V1000CT-2). Additional scenarios are defined for code-to-code comparison. As a 3D core model is necessary for a best-estimate computation of all the scenarios of the V1000CT benchmark, all participants were asked to develop their own core coupled 3D thermal-hydraulics/neutron kinetics models using the data available in the benchmark specifications and a common cross-section library. The first code-to-code comparisons based on the V1000CT-1 Exercise 2 specifications exhibited unacceptable discrepancies between two sets of results. The present paper focuses on the analysis of the observed discrepancies. The VVER-1000 3D neutron kinetics models are based on cross-section data homogenized on the assembly level. The cross-section library, provided as part of the benchmark specifications, thus consists in a set of parameterized two group cross sections representing the different assemblies and the reflectors. The origin of the observed large discrepancies was found mainly to lie in the methods used to solve the diffusion equation. The VVER reflector properties were also found to enhance discrepancies by increasing flux gradients at the core/reflector interface thus highlighting more the difficulties in some codes to handle high exponential flux gradients. This paper summarizes the different steps applied to analyze the neutronic codes and their predictions as well as the impact of cross-section generation procedures.