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     

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。     

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.     

一种基于成像板的能量卡阈式快中子图像测量方法

为减小散射中子等较低能量的中子对快中子图像的贡献,提出了在成像板前依次紧贴金属卡阈片和富氢元素薄片的能量卡阈式快中子成像方法.该方法通过改变卡阈片材料、厚度等参数,可有效降低成像结构对某一能段中子的相对灵敏度.以14 MeV中子照相为例设计的能量卡阈式成像结构为TR成像板依次覆盖约150μm Pb膜和500μm聚乙烯膜,计算表明该结构对8 MeV以下快中子灵敏度小于其对14 MeV中子灵敏度的30%.利用K400加速器DT中子源开展了验证实验,结果表明能量卡阈式快中子成像结构能够有效消除样品散射中子引起的边界增强效应.     

Gamma全吸收型BaF2探测装置中子屏蔽体与吸收体的研究

中国原子能科学研究院已经建造完成了我国第一套全吸收型BaF₂探测装置,采用瞬发γ测量法,精确测量中子俘获反应截面。中子源是利用HI-13串列加速器产生的脉冲化质子束,通过7Li(p, n)7Be反应建立。为了有效降低周围环境材料和探测器产生的散射中子本底,约束中子束流的形状,使用MCNP程序模拟设计了屏蔽体,采用含硼聚乙烯(B₄C质量分数为5%)包裹5 cm铅的方案,以及准直器采用平行孔的方案。该设计使样品处的中子束斑平整均匀,直径约为2 cm,束斑外的中子注量降低5个数量级,γ注量降低3个数量级。同时设计了中子吸收体(外半径为10 cm,厚度为7 cm)用于吸收待测样品产生的散射中子。MCNP和GEANT4程序的模拟结果表明:选择含硼聚乙烯(10B₄C质量分数为10%)作为中子吸收体的加工材料,其中子吸收率达到了80%,并设置1 MeV的能量加和阈,能够满足在线测量中子俘获反应截面的实验要求。     

静态随机存储器单粒子翻转的Monte Carlo模拟

利用蒙特卡罗(Monte Carlo)方法，对10—20MeV 中子在静态随机存储器(SRAM)中引起的单粒子翻转进行了模拟，着重对中子在SRAM 灵敏区引起的电离能量沉积进行了计算，并对中子引起单粒子翻转过程相关物理量进行了计算.这些计算模拟结果为了解10—20MeV 中子引起SRAM 单粒子翻转过程提供了详细的统计信息，为SRAM 的抗辐射加固提供相关参考信息. 关键词： SRAM单粒子翻转 Monte Carlo 模拟 能量沉积     

8.19 MeV中子与9Be作用的次级中子双微分截面测量

用中国原子能科学研究院HI13串列加速器上的多探测器快中子飞行时间谱仪, 测量了8.19 MeV中子与9Be作用时, 从20°到160°区间26个角度的次级中子双微分截面。测量截面以np散射截面作为标准进行归一。实验结果用Monte Carlo方法进行了中子注量率衰减、多次散射和有限几何修正, 并用MCNP4C程序对所用的Monte Carlo程序进行了验证。测量结果与评价数据以及其它实验室的数据进行了比较。The secondary neutron emission double differential cross section of 9Be induced by 8.19 MeV neutron was measured at 26 different angles from 20°to 150°by using the multi detector fast neutron TOF spectrometer at the HI 13 Tandem Accelerator at China Institute of Atomic Energy(CIAE). The results were normalized to np scattering measurement. A special Monte Carlo code which was validated with the MCNP 4C code was employed to analyze the measured data for the corrections of neutron flux attenuation, multiple scattering and finite geometry. The measured results were compared with the evaluated data and the other measurements.      

基于蒙特卡罗模拟研究锆钛酸铅镧材料的中子辐照损伤

锆钛酸铅镧(Pb_0.94La_0.06Zr_0.96Ti_0.04O₃,PLZT)具有良好的介电和储能性质,是高效、高能量密度电容元件和存储器件的基体材料.为研究该材料的中子辐照损伤,首先基于Geant4程序包模拟了能量为1—14 MeV中子辐照浩钛酸铅镧(PLZT)材料产生的反冲原子能谱,然后根据产生的反冲原子种类和最大能量,利用二元碰撞方法模拟了不同能量的离子在PLZT中产生的位移损伤(包括空位和间隙原子),最后根据反冲原子能谱和对应能量离子在材料中产生的缺陷数目计算了不同能量的中子在PLZT材料中产生缺陷浓度以及分布.结果发现,对于1—14 MeV能区的快中子而言,其在厚度为3 cm的PLZT材料中产生的缺陷数目近似与中子能量无关,约为460±120空位/中子.辐照损伤在3cm厚度内随深度的增加而略有减小,总体变化小于50%,该减小主要是由于中子的反散射导致.本工作为计算中子在材料中的位移损伤提供了一种方法,同时模拟结果可为研究PLZT基电子器件的中子辐照效应提供指导.     

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.     

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.     

241Am-Be中子参考辐射的蒙特卡罗模拟研究

研究用于校准场所中子剂量监测仪表的241Am-Be中子参考辐射场计量特性。采用蒙特卡罗方法模拟了空气自由中子参考辐射(FRNR),GB/T 14055规定的最小尺寸中子参考辐射(SRNR)和实际中子参考辐射(ARNR)中不同检验点处中子周围剂量当量率、散射中子占比和能谱分布特征。研究结果表明,空气对FRNR中的剂量率和能谱分布影响小,近似为理想中子参考辐射;采用5%含硼聚乙烯作屏蔽的最小尺寸SRNR可减少热中子,降低散射中子占比,影锥法不适用于小尺寸中子参考辐射中对散射中子的修正;ARNR中的散射中子更少、占比更低,影锥法所得散射中子占比与理论值基本一致。     

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CCD成像系统反射镜引入本底分析

 在基于CCD相机的中子照相系统中,反射镜距离闪烁屏太近就会将部分荧光反射回闪烁屏,将闪烁屏照亮,入射中子束的少部分还会被反向散射回闪烁屏,形成图像本底叠加在图像上,对定量分析和CT重建结果产生影响。为此建立了反射镜所引入反射分量的计算方法,可根据闪烁屏受照分布和反射镜参数计算反射分量的分布,并对中子反向散射进行了蒙特卡罗模拟,计算结果与实验测量的本底分布规律相符。     

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.     

Characterization of a BNCT beam using neutron activation and indirect neutron radiography

This study aims to measure the neutronic characteristics of the 14-cm diameter boron neutron capture therapy beam at the Tsing Hua Open-pool Reactor and to provide essential information for the neutron source adjustment and validation. The measurements were performed both in air and inside a cubic PMMA phantom at the beam, with and without an 18-cm long extended PE collimator. The neutron intensity was determined by neutron activation analysis; the indirect neutron radiography and the cadmium difference method were coupled to provide the two-dimensional neutron flux distributions.According to the measurements, the angular distribution is highly forward for epithermal neutrons but much more divergent for thermal ones. A PE extended collimator will modify the beam characteristics and could benefit the treatment for head and neck tumors, which often needs higher therapeutical boron dose at the shallow region.     

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。     

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)