14MeV中子照相中散射中子对成像影响的Monte Carlo模拟

依据实验参数，建立了14MeV快中子照相的物理模型，并利用Monte Carlo方法对照相过程进行了模拟. 分析了经聚乙烯样品散射的中子对快中子图像的影响随样品与探测器间距及样品参数的变化. 计算结果表明，样品与探测器的距离d<5cm时，样品中的散射中子对图像的影响强烈依赖于d，而当d>20cm时，样品散射中子对图像的影响可忽略；当样品密度为3—5g/cm³时散射中子对图像的影响相对最大；样品宽度越大，图像中的散射成分越多，当宽度在3cm以上时散射成分的强度趋于饱和. 关键词： 14MeV中子 快中子照相 散射中子 Monte Carlo模拟     

快中子照相胶片成像法的初步实验

利用9Be(d,n)反应在北京大学4.5MV静电加速器上产生小于7MeV能区的快中子,采用胶片法进行了快中子照相的初步实验.对快中子胶片成像法的基本性能进行了初步的测试和研究.用国产的原材料研制了一种适用于快中子照相的关键部件－快中子转换屏.实验结果表明研制的快中子转换屏能够满足快中子照相的需要.A preliminary experiment is conducted with direct film method under the condition that fast neutron is generated by the reaction of 9Be (d,n) on the Peking University 4.5 MV Van de Graff, whose energy is lower than 7 MeV.Basic characteristics of direct-film neutron radiography system is researched with the help of samples in different materials, different thickness and holes of different diameter. The fast neutron converter, which is vital for fast neutron imaging, is produced with the materials made in china. The result indicates that fast neutron converter can meet the requirment of fast neutron imaging; what's more, further research of fast neutron imaging can be conducted on the accelerator and neutron-generator in China.     

厚闪烁体内次级中子对快中子图像质量的影响研究

利用编制的快中子照相数值模拟程序(FNRSC)模拟计算了入射中子能量为14 MeV时,厚度5—300 mm闪烁体内次级中子对快中子图像质量的影响,结果表明闪烁体厚度d<50mm时,次级中子对图像的影响强烈依赖于闪烁体厚度,而当d>50 mm时,次级中子对图像的影响趋于饱和.将文献中利用蒙特卡罗中子-光子输运程序(MCNP)计算的次级中子对图像影响和文中计算结果进行了对比,给出了二者存在差异的主要原因：次级中子分布对入射中子空间分布的强烈依赖性;能量沉积和荧光输出这两种计算方法对 关键词： 14 MeV中子 快中子照相 次级中子 Monte Carlo模拟     

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.     

利用数值模拟测量闪光照相中H-D曲线

在分析高能闪光照相中传统实验方法不足的基础上,提出了采用Monte Carlo模拟结果来建立底片光学密度与照射量之间的关系,并对一个球对称客体进行了实验照相。采用Monte Carlo方法分析了底片光学密度分布左右不对称的各种因素,认为底片光学密度分布左右不对称主要是照相器件几何对中不理想造成的,并说明了底片光学密度左右平均的合理性。在此基础上介绍了H-D曲线的生成方法,采用Silberstein理论得到了具有较高精度的H D曲线。这种结合Monte Carlo模拟的H-D曲线测量方法不但避免了照射量测量误差,而且还考虑了H-D曲线对X射线能谱的依赖关系,更能体现实际情况,具有较高的精度。可用于球对称客体或柱对称客体的辐射照相。     

利用数值模拟测量闪光照相中H-D曲线

 在分析高能闪光照相中传统实验方法不足的基础上,提出了采用Monte Carlo模拟结果来建立底片光学密度与照射量之间的关系,并对一个球对称客体进行了实验照相。采用Monte Carlo方法分析了底片光学密度分布左右不对称的各种因素,认为底片光学密度分布左右不对称主要是照相器件几何对中不理想造成的,并说明了底片光学密度左右平均的合理性。在此基础上介绍了H-D曲线的生成方法,采用Silberstein理论得到了具有较高精度的H D曲线。这种结合Monte Carlo模拟的H-D曲线测量方法不但避免了照射量测量误差,而且还考虑了H-D曲线对X射线能谱的依赖关系,更能体现实际情况,具有较高的精度。可用于球对称客体或柱对称客体的辐射照相。     

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。     

快中子照相中的点扩展函数计算

快中子照相中,基于反冲核原理探测快中子的有机闪烁体平板是普遍采用的快中子辐射转换体。模拟了D-T中子垂直入射BC400闪烁体平板,计算了不同厚度平板闪烁体的点扩展函数,对14.1 MeV快中子照相中闪烁体固有分辨率随厚度的变化进行了研究。计算结果表明,在不考虑二次中子与闪烁体作用及背景噪声等情况时,点扩展函数几乎不依赖于闪烁体厚度。同时,计算还表明在一定的分辨率范围内,由于荧光收集效率的限制,闪烁体厚度增加并不会改善图像对比度。     

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。     

快中子照相中的点扩展函数计算

 快中子照相中,基于反冲核原理探测快中子的有机闪烁体平板是普遍采用的快中子辐射转换体。模拟了D-T中子垂直入射BC400闪烁体平板,计算了不同厚度平板闪烁体的点扩展函数,对14.1 MeV快中子照相中闪烁体固有分辨率随厚度的变化进行了研究。计算结果表明,在不考虑二次中子与闪烁体作用及背景噪声等情况时,点扩展函数几乎不依赖于闪烁体厚度。同时,计算还表明在一定的分辨率范围内,由于荧光收集效率的限制,闪烁体厚度增加并不会改善图像对比度。     

Numerical study of point spread function of a fast neutron radiography system based on scintillating-fiber array

For a scintillating-fiber array fast-neutron radiography system, a point-spread- function computing model was introduced, and the simulation code was developed. The results of calculation show that fast-neutron radiographs vary with the size of fast neutron sources, the size of fiber cross-section and the imaging geometry. The results suggest that the following qualifications are helpful for a good point spread function: The cross-section of scintillating fibers not greater than 200μm×200μm, the size of neutron source as small as a few millimeters, the distance between the source and the scintillating fiber array greater than 1 m, and inspected samples placed as close as possible to the array. The results give suggestions not only to experiment considerations but also to the estimation of spatial resolution for a specific system.     

The pilot experimental study of 14 MeV fast neutron digital radiography

14 MeV Fast neutrons has good penetrability and the 14 MeV fast neutron radiography can meet the need of Non-Destructive Test of the structure and lacuna of heavy-massive sample, whose shell is made of heavy metal and in which there are some hydrogen materials, and the study of fast neutron digital radiography just begins in China. By the use of a D-T accelerator, a digital imaging system made up of a fast neutron scintillation screen made of ZnS(Ag) and polypropylene, lens and a scientific grade CCD, the experimental study of fast neutron radiography has been done between 4.3×10¹⁰−6.8×10¹⁰ n/s of neutron yield. Some 14 MeV fast neutron digital radiographs have been gotten. According to experimental radiographs and their data, the performance of the fast neutron scintillation screen and the basic characters of 14 MeV fast neutron radiography are analyzed, and it is helpful for the further research. Supported by the Science and Technology Fund of China Academy of Engineering Physics (Grant No. 251)     

An empirical formula for scattered neutron components in fast neutron radiography

Scattering neutrons are one of the key factors that may affect the images of fast neutron radiog- raphy. In this paper, a mathematical model for scattered neutrons is developed on a cylinder sample, and an empirical formula for scattered neutrons is obtained. According to the results given by Monte Carlo methods, the parameters in the empirical formula are obtained with curve fitting, which confirms the logicality of the empirical formula. The curve-fitted parameters of common materials such as <'6>LiD are given.     

中子照相数值模拟与实验的对比

介绍了热中子照相的MCNP数值模拟方法,模拟了300＃反应堆Maxwell谱热中子束穿透样品射到转换屏的过程,给出了热中子对铝、铅、铁、铜的穿透能力,分析了引起模拟与实验结果不同的原因。通过模拟得到了清晰的图像,对比数值模拟与在300#反应堆中子照相装置上的实验结果,数值模拟结果图像与实验结果图像非常相似;散射中子对图像的影响也符合相同的规律,随着样品与转换屏之间的距离的增大,散射中子对结果图像的影响越来越小,当样品与转换屏之间的距离为样品尺寸的2倍时可以忽略散射中子的影响。     

An empirical formula for scattered neutron components in fast neutron radiography

Scattering neutrons are one of the key factors that may affect the images of fast neutron radiography. In this paper, a mathematical model for scattered neutrons is developed on a cylinder sample, and an empirical formula for scattered neutrons is obtained. According to the results given by Monte Carlo methods, the parameters in the empirical formula are obtained with curve fitting, which confirms the logicality of the empirical formula. The curve-fitted parameters of common materials such as ⁶LiD are given.     

数值模拟高能中子照相

模拟了14 MeV中子在穿透样品后与闪烁体光纤的作用。对每根光纤中的能量沉积进行了计算,并转换成可见光(496 nm)光子数。在模拟实验中,分析了影响图像质量的因素。计算了散射中子本底与闪烁体和样品(聚乙烯)间距的关系。当间距为cm量级时,散射中子本底对图像的影响很小。计算表明系统对样品的甄别厚度与入射中子总数有关,在一定范围内近似与中子总数的对数成线性关系。通过模拟结果给出了理想平行中子束入射情况下系统的平面分辨率。     

中子照相数值模拟与实验的对比

 介绍了热中子照相的MCNP数值模拟方法,模拟了300＃反应堆Maxwell谱热中子束穿透样品射到转换屏的过程,给出了热中子对铝、铅、铁、铜的穿透能力,分析了引起模拟与实验结果不同的原因。通过模拟得到了清晰的图像,对比数值模拟与在300#反应堆中子照相装置上的实验结果,数值模拟结果图像与实验结果图像非常相似;散射中子对图像的影响也符合相同的规律,随着样品与转换屏之间的距离的增大,散射中子对结果图像的影响越来越小,当样品与转换屏之间的距离为样品尺寸的2倍时可以忽略散射中子的影响。     

高灵敏度的快中子照相系统

快中子照相系统由闪烁光纤阵列和科学级可见光CCD等元件组成. 14 MeVD-T聚变中子在穿透样品后进入50 mm×50 mm闪烁光纤阵列，中子辐射转换为中心波长496 nm的绿光. 光纤阵列长100 mm，光纤截面500 μm×500 μm，100×100根闪烁体光纤组成阵列. 阵列对14 MeV中子探测效率经估算可达21.4%. CCD与光纤阵列之间采用反射镜和透镜耦合方式，使CCD避开中子源直接辐照. 综合考虑光纤尺寸、CCD记录噪声及中子源与受照样品几何关系等因素，理论上系统可获得整体分辨率1.5 mm的中子图像. 在K400直流加速器中子源上进行了初步实验，获得了中子图像.