可移动式中子监测隐性爆炸物系统的初步探索与研究

瞬发γ中子活化分析技术具有快速、原位、不需取样、准确、灵敏度高且能够实时多核素在线分析的特点,因此该技术是监测隐性爆炸物,尤其是非金属类爆炸物的最有效手段之一.在国内外有不少科技工作者对中子法监测隐性爆炸物技术进行了大量的研究,并取得了一定的成绩.主要对中子技术探测地雷和隐性爆炸物的各种方法和技术路线进行讨论,对同位素镅铍中子源和14 MeV脉冲中子管活化分析方法进行了初步探索研究,并对可移动式系统的源探的几何布置进行了探讨.Because it can on line analyze many elements quickly and precisely without sampling and movement, prompt gamma neutron activation analysis is one of the most effective methods to monitor latent dynamite especially nonmetal. Many researchers studied the neutron detecting latent dynamite technique and get some achievements. This paper mainly discussed each method and technology route of neutron detecting landmine and latent dynamite, studied the Am Be isotope neutron source and 14 MeV pulse neutron tube activation analysis, and analyzed the geometrical layout of movable system.     

Measurement of velocity distribution in an atomic beam by means of Doppler resonance fluorescence

Introduction Measurement of velocity distribution in atomic beams is of significance to laser spec-troscopy and atomic physics.Previously,workers used to investigate atomic velocity distribu-tion by means of mechanic separators.Recently, spectroscopic methods of measuring veloc-ity distribution are developed,which find velocity distribution from detecting atomic fluo-rescence frequency distribution or from detecting atomic deflection due to radiation force.Un-fortunately,these methods can not realize real time measurement.In this paper we propose a     

中子检测隐藏爆炸物技术的研究进展

对中子检测隐藏爆炸物技术的基本原理作了较详细的介绍,对几种不同的检测方法进行了比较,分析了当前国内外的研究现状,并指出了未来的发展方向。In this paper, several methods and basic principles of neutron detecting latent explosive are introduced and analyzed in details. The progresses in this field are reviewed and further development direction is also prospected.     

用放射性测量技术识别化学毒剂

简单介绍了非破坏性识别化学毒剂技术 ,研究了中子诱发 γ谱法、热中子氢含量测量和 X射线成像技术等放射性测量技术识别化学毒剂的原理和实际使用中的一些问题.There are three non destructive radiological methods for identitication of warfare agents and TNT. Their principles and problems related were discussed. Portable isotopic neutron spectroscopy is based on the assay of key elemental composition (such as Cl, P, H, As, S, N) in chemical agents by neutron induced prompt gamma ray analysis. Hydrogen concentration measurement by means of using thermal neutron can be exployed to identify chemical warfare agents and TNT...     

基于D-T紧凑型中子源的快中子照相准直屏蔽体设计及中子束特性模拟研究

中子照相是一种重要的无损检测技术,它能用于火工产品、毒品和核燃料元件等的检测。基于紧凑型D-T中子发生器,完成了一个用于快中子照相的准直屏蔽体系统（BSA）的物理设计。根据D-T中子源的能谱和角分布建立了中子源模型,采用MCNP4C蒙特卡罗程序,模拟了准直屏蔽体系统中中子和γ射线的输运,准直中子束相对于单位源中子的中子注量可以达到9.30×10-6 cm-2,准直中子束中主要是能量大于10 MeV的快中子;在设置的样品平面直径14 cm的照射视野范围,准直束中子注量的不均匀度为4.30%,准直束中中子注量与γ注量的比值为17.20,中子通量和中子注量比值J/Φ为0.992,说明准直中子束有好的平行性;准直屏蔽体外的泄露中子注量率与准直束中子注量率相比降低了2个量级。所设计的准直屏蔽体能满足快中子照相的要求。Neutron radiography is an important nondestructive testing technique. It can be used to detect the explosive devices, drug and the nuclear fuel element, etc. A beam-shaping-assembly (BSA) based on a compact D-T neutron generator is designed for fast neutron radiography in this paper. D-T neutron source model is constructed based on the neutron energy spectrum and angular distribution data. The transportation of neutron and γ-ray in the BSA is simulated using MCNP4C code. The neutron fluence of the collimated neutron beam with respect to the neutron source of the unit source is 9.30×10-6 cm-2. The collimated neutron beams is mainly fast neutrons with energies greater than 10 MeV. In the irradiation field range with a diameter of 14 cm, the neutron fluence uniformity of the collimated beam is 4.3%, the ratio of the neutron fluence to the gamma fluence in the collimated beam is 17.20, and the neutron flux and the neutron fluence ratio (J/Φ) is 0.992 which indicates that the collimated neutron beam has good parallelism. The leakage neutron fluence in outside of BSA is two orders of magnitude lower than that of the collimated neutron beam. The designed BSA can meet the need of fast neutron radiography.     

Development of the Tiny Current Test of nA

The sensor of ray made use of photosensitive element translate the light signal into the electric signal, its keenness wavelength is by wavelength of observable ray, includes the infrared＇s wavelength and ultraviolet radiation＇s wavelengthth. The sensor of ray is not only used for detecting ray but also used for composing the other sensor. It can detect many non-electric signal, the premise should translate the non-electric signal into the light signal. The sensor of ray is a sort of most output and application being most extensive, it is very important in the field of automatic control and none-electric test art.     

Track before detect for point targets with particle filter in infrared image sequences

The problem of detecting and tracking point targets in a sequence of infrared images with very low signalto-noise ratio (SNR) is investigated in this paper. A track before detect algorithm for infrared (IR) point target is developed based on particle filter. The particle filter is used to estimate the state of the target in track stage. The unnormalized weights of the output of the filter are used to approximately construct the likelihood ratio for hypothesis test in detection stage. Experiment results with the real image sequences that SNR is about 2.0 show that the proposed algorithm can successfully detect and track point target.     

Track before detect for point targets with particle filter in infrared image sequences

The problem of detecting and tracking point targets in a sequence of infrared images with very low signalto-noise ratio (SNR) is investigated in this paper. A track before detect algorithm for infrared (IR) point target is developed based on particle filter. The particle filter is used to estimate the state of the target in track stage. The unnormalized weights of the output of the filter are used to approximately construct the likelihood ratio for hypothesis test in detection stage. Experiment results with the real image sequences that SNR is about 2.0 show that the proposed algorithm can successfully detect and track point target.     

Improvement of the determination of hydrogen content in a multicomponent sample by D—T generator

If a D T generator is used as a neutron source to simultaneously measure the content of carbon, hydrogen and oxygen in a multicomponent sample by NIPGA （Neutron Induced Prompt Gamma-ray Analysis）, the 14 MeV neutron flux can be regarded as a constant value. The relationship between the production of the hydrogen characteristic gamma-rays and its content is nonlinear. In this paper, we use MCNP （Monte Carlo N-Particle Transport code） to simulate the relationship and analyze it. In practical measurement of the characteristic gamma-ray, it＇s impossible to get the net count. Therefore, we use the experiment to obtain the relationship between the hydrogen content and the total count of its characteristic gamma-rays. If we use the relationship combined with the simulation result to calculate the hydrogen content, the metrical precision can be much increased. The deviation of hydrogen content between NIPGA and chemical analysis is less than 0.25%, which meets the requirement of coal industry.     

The focus steering for high intensity focused ultrasound phased array based on real-time phase shift calculation

When time reversal technique is used in phased array high intensity focused ultrasound system to obtain self-adaptive focusing,it is needed to calculate the initial phases of the elements.Because of the frequency oscillation when the phase lock loop is initiated,different results are got in different segments using conventional methods.A method of calculating the phase difference was presented,that can display the changes of phase difference in real-time, and the steady phase differences can be regarded as the initial phases of the elements.The experimental results show that using the phase difference obtained by this method can get a better distribution of sound field in a certain spatial region.     

组合PIN脉冲中子探测器灵敏度研究

对新型组合PIN脉冲中子探测器的灵敏度进行了研究,实验测量探测器的DT中子灵敏度和γ相对灵敏度,用Monte?Carlo方法计算了探测器的中子灵敏度.实验测量和计算表明:通过转换靶的选取,组合PIN探测器的中子灵敏度在一定范围内连续可调,组合PIN探测器对γ的灵敏度比普通PIN探测器低2个量级,是一种对γ不灵敏的新型脉冲中子探测器.     

以中子作外源的假想核弹头主动探测

通过对不同入射能量的中子在假想的核弹头中的输运计算,分析了弹头中的裂变材料芯部的核裂变、各层对中子的吸收和(n,xn)反应以及出壳中子随角度的变化,论证了以外中子源(不随时间变化的外源)对弹头作主动探测的可行性.通过对14 1MeV脉冲中子源和产生的缓发中子在模型中的输运计算,分析了用脉冲外中子源产生的缓发中子探测核弹头的可行性.     

移动式加速器在快中子照相中的应用

介绍了移动式加速器的工作原理、结构和调试过程。该加速器具有体积小、重量轻、束流稳定度高、束斑直径小的特点。移动式加速器是首次在中国工程物理研究院应用于快中子照相。在调试过程中测试了小型移动式加速器的束流稳定性等参数,采用伴随粒子方法测量了直流中子产额。通过移动加速器和数字照相系统的组合,获得了初步图像。     

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利用蒙特卡罗粒子输运程序(MCNP)对氦冷固态增殖剂包层聚变示范堆(HCSB DEMO)做了中子通量谱分析。根据中子通量谱特点选出活化片材料,根据跑兔系统和活化片法测中子通量的原理设计出适用于测量HCSB DEMO增殖包层中子的活化片法测量系统,并对其各组成部分及功能做了说明。计算了活化片在测量系统辐照端辐照时的活化反应率、活化片特征γ射线发射率及特征γ计数率,并得到一套合理的测量方案,用于HCSB DEMO包层中子的测量。     

5单元中子散射相机仿真研究

采用粒子输运程序MCNP与FORTRAN,MATLAB程序相结合,对一种5单元结构的中子散射相机原型进行了蒙特卡罗模拟,对252Cf裂变中子源进行了图像、能量的重建。结果表明:该相机的能量分辨力为9%左右,角分辨与闪烁体的体积有关;中子能量为2 MeV左右时,散射相机的探测效率达到最大值;源的距离、闪烁体尺寸、前后面板距离、事件数等对重建图像的分辨力都有不同程度的影响;散射相机可以获得裂变中子源的能谱形状,但系统的结构、探测阈值等会使能谱测量造成一定的偏差。该理论工作的结论可推广到由更多单元组成的散射相机中使用。     

HCSB DEMO 中子通量谱分析及活化片法测量系统概念设计研究

利用蒙特卡罗粒子输运程序(MCNP)对氦冷固态增殖剂包层聚变示范堆(HCSB DEMO)做了中子通量谱分析。根据中子通量谱特点选出活化片材料,根据跑兔系统和活化片法测中子通量的原理设计出适用于测量HCSB DEMO 增殖包层中子的活化片法测量系统,并对其各组成部分及功能做了说明。计算了活化片在测量系统辐照端辐照时的活化反应率、活化片特征γ 射线发射率及特征γ 计数率,并得到一套合理的测量方案,用于HCSB DEMO 包层中子的测量。     

中子散射对快中子照相质量影响的分析

通过一内空的圆柱体模型，对在快中子照相时由样品引起的散射中子强度与样品形状和探测距离之间的关系进行模拟，并用^241Am—Be作中子源对散射中子的影响进行实验验证。结果表明，在快中子照相时，由样品引起的散射中子的强度与探测距离以及样品形状有关。对于同一样品，探测距离增加，散射中子的影响则降低。The relationships between intensities of scattered neutrons by specimens and their shapes and detecting distances have been simulated using a hollow cylinder model, and the results were validated by experiments of fast neutron imaging using ^241Am-Be neutron source. The results showed that the intensities of scattered neutrons are closely related to the detecting distances and sample＇ s shapes. The influences of scattered neutronns in fast neutron imaging will be reduced while detecting distances increased.