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。     

ST401塑料闪烁体的脉冲中子相对光产额评估方法

介绍了脉冲中子在ST401塑料闪烁体上的相对光产额评估方法.采用Geant4蒙特卡罗软件模拟X射线和中子在闪烁体中的输运行为,记录产生的全部带电粒子类型和能量,由公式计算得到相对光产额.给出了不同能量的单个中子和单个X射线入射到1 mm,3 mm,5 mm,1 cm,2 cm,3 cm,5 cm厚ST401的平均相对光产额.在0.3 MeV脉冲X射线源和14 MeV脉冲中子源上开展验证实验,采用相同的图像测量系统记录相对光产额,给出了单个中子与X射线的平均相对光产额比值.模拟结果与实验结果相对误差小于10%.结果可以为宽能谱脉冲中子束图像测量系统的量程安排提供依据.     

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。     

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     

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。     

D—D中子在聚乙烯球壳内的反应率测量

开展D-D聚变中子与聚乙烯球壳作用的中子学积分实验，用于检验计算方法和相关核数据。实验装置由D—D中子源与聚乙烯球壳组成，中子源在聚乙烯球壳外，距球壳外表面35mm。聚乙烯球壳由两个半球壳组成，外径φ386mm，厚度100mm。聚乙烯球壳中心与靶心的轴线水平。     

一维时空分辨x射线辐射功率测量系统

采用狭逢、红光闪烁体、光纤阵列、条纹相机、像增强器等元件组成x射线辐射功率时空分辨测量系统，该系统具有对x射线能量响应平坦，可有效屏蔽本底光干扰的优点，在喷气Z pinch实验中成功获得内爆等离子体x射线辐射的轴向分布图像.文中对系统结构、参数和使用情况进行了介绍，对测量结果进行了讨论. 关键词： Z pinch x射线 时空分辨 图像     

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。     

CCD相机对14MeV和2.5MeV中子瞬态响应特性

从理论上分析了中子在CCD相机拍摄图像中引起的瞬态干扰噪声的机理,并针对两种不同类型的CCD相机,在能量为14MeV和2.5MeV的低强度稳态中子源上开展了实验研究,分析了噪声特征与入射中子能量、入射角度、注量及CCD相机结构的关系。实验结果表明中子瞬态干扰噪声主要表现为脉冲噪声,且出现斑点现象,与理论分析结果相吻合。研究得出了噪声特征随入射中子注量变化的规律,比较了不同能量及不同入射角条件下的噪声特性,并分析了两种不同结构的CCD相机响应特性的差别。     

CCD相机对14 MeV和2.5 MeV中子瞬态响应特性

从理论上分析了中子在CCD相机拍摄图像中引起的瞬态干扰噪声的机理,并针对两种不同类型的CCD相机,在能量为14 MeV和2.5 MeV的低强度稳态中子源上开展了实验研究,分析了噪声特征与入射中子能量、入射角度、注量及CCD相机结构的关系。实验结果表明中子瞬态干扰噪声主要表现为脉冲噪声,且出现斑点现象,与理论分析结果相吻合。研究得出了噪声特征随入射中子注量变化的规律,比较了不同能量及不同入射角条件下的噪声特性,并分析了两种不同结构的CCD相机响应特性的差别。     

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)     

Stand for testing scintillation neutron detectors

A stand for studying the characteristics of time-of-flight neutron detectors is described. Plastic scintillation detectors in the form of rectangular prisms with cross sections of 100 × 100 and 100 × 200 mm² and lengths of 300, 400, and 500 mm are viewed through by photomultipliers from the two ends. The detectors are irradiated with a collimated 14-MeV neutron beam produced in the d + t → n+ ⁴He reaction. The collimated beam makes it possible to investigate the spatial resolution of long detectors. The interaction point is determined either from the arrival time of light pulses to the opposite ends of the scintillators or from the ratio of the amplitudes of the signals at the ends of the scintillators. The stand proposed also makes it possible to measure the absolute efficiency of detectors of different length at a neutron energy of 14 MeV.     

Determination of Moisture Content in Coke with <Superscript>239</Superscript>Pu–Be Neutron Source and BGO Scintillation Gamma Detector

A series of experiments has been conducted at the Frank Laboratory of Neutron Physics (FLNP) of the Joint Institute for Nuclear Research (JINR) in order to study the possibility of determining the moisture content of coke using a standard neutron source. The proposed method is based on a measurement of the spectrum of prompt γ rays emitted when samples are irradiated by fast and/or thermal neutrons. The moisture content is determined from the area of the peaks of characteristic γ rays produced in the radiative capture of thermal neutrons by the proton (E_γ = 2.223 MeV) and inelastic scattering of fast neutrons by ¹⁶O (E_γ = 6.109 MeV). The ²³⁹Pu–Be neutron source (〈E _n 〉 ~ 4.5 MeV) with an intensity of ~5 × 10⁶ n/s was used to irradiate the samples under study. A scintillation detector based on a BGO crystal was used to register the characteristic γ radiation from the inelastic fast neutron scattering and slow (thermal) neutron capture. This paper presents the results of humidity measurement in the range of 2–50% [1, 2].     

Measurement of the response function and the detection efficiency of an organic liquid scintillator for neutrons between 1 and 30 MeV

The light output function of a φ50.8 mm×50.8 mm BC501A scintillation detector was measured in the neutron energy region of 1 to 30 MeV by fitting the pulse height (PH) spectra for neutrons with the simulations from the NRESP code at the edge range. Using the new light output function, the neutron detection efficiency was determined with two Monte-Carlo codes, NEFF and SCINFUL. The calculated efficiency was corrected by comparing the simulated PH spectra with the measured ones. The determined efficiency was verified at the near threshold region and normalized with a Proton-Recoil-Telescope (PRT) at the 8-14 MeV energy region.     

A pulsed neutron source on the proton beam for the Moscow Meson Factory

A new pulsed neutron source based on a beam-blanking device has been under construction and improvement at the Moscow Meson Factory of the Institute for Nuclear Research of the Russian Academy of Sciences. Neutrons are generated in the course of the spallation process in a water-cooled tungsten target by a proton beam with an energy of 209 MeV. After water moderator (3 cm), neutrons are guided in three horizontal and one vertical channels with a length varying from 4 to 50 m. The standard duration of the proton pulse from the accelerator is 60 μs. At present, the average proton current is as high as 150 μA for a repetition rate of 50 Hz. The neutron fluence in the target is equal to 0.9 × 10¹⁵ neutrons/s, which corresponds to the requirements imposed on the intensity of modern pulsed neutron sources.