中子源有源法核查技术研究

用有源 (主动 )方法研究了贫化铀组合系统的中子诱发裂变缓发中子探测技术 .在不同屏蔽和组合等条件下测量和比较了贫化铀系统的缓发裂变中子分布 ,进一步研究了实验系统的可核查性 .探讨了区分核与非核系统的方法. The technique for detecting the delayed neutrons from neutron induced fission in uranium systems was studied by using an active method with 3He proportional counting tube array and a 14 MeV D T neutron source. Under the conditions of different shielding and combination, the distributions of delayed fission neutrons from depleted uranium systems were measured and the reliability of the systems was studied. The method to distinguish a nuclear system from a non nuclear one was discussed.     

中子俘获瞬发γ活化分析数据库

简要地介绍了热中子俘获瞬发γ射线数据的测量、评价、检验及其中子俘获瞬发γ射线活化分析数据库的研制、结构和基本数据内容等. The evaluation, measurement, and check of prompt γ-ray data for neutron capture are presented. The development of the database of prompt γ-ray activation analysis for neutron capture, and its structure and basical data are also described in the text.     

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.     

中子检测爆炸物的原理实验研究

传统的X射线无损检测应用广泛, 但X射线对低原子序素构成为主的爆炸物不能进行有效的甄别; 中子穿透能力较强, 能和原子核相互作用产生特征γ射线, 因此中子无损检测方法能有效弥补X射线无损检测方法的不足。 介绍了几种常用的中子无损检测方法, 并采用脉冲快热中子法（为PFTNA）的方法对模拟爆炸物进行了测量。 实验结果表明, 利用密封中子发生器和采用PFTNA方法进行爆炸物检测是可行的。 Traditional X ray scatheless detecting method is used widely, but it is not useful to discriminate explosive consisting of low Z atomic elements. The penetrability of neutron is much better, and it can interact on atomic nucleus to emit characteristic γ ray. So neutron scatheless detecting methods can the used to detect the low Z atomic elements. In this paper, several neutron scatheless detecting methods are introduced briefly, and the principium experiment using Pulse Fast Thermal Neutron Analysis(PETNA) to detect a kind of explosive simulacrum is carried out. The experiment results show that PFTNA based on the sealed neutron generator is feasible to detect explosive.     

塑料闪烁体中子探测效率及相对发光产额的标定

利用加速器中子源研究了用于标定塑料闪烁体中子探测效率及相对发光产额的实验技术 ,在四川大学原子核科学技术研究所 2 .5MeV静电加速器上 ,利用T(p,n)和D(d ,n)核反应作为中子源 ,在 0 .6—5MeV中子能区对直径为 40mm ,厚度为 5mm的 1 42 1塑料闪烁体的中子探测效率及相对发光产额进行了测定.A method used for the calibration of neutron efficiency and the relative photo yield of plastic scintillator is studied. T(p,n) and D(d,n) reactions are used as neutron resources. The neutron efficiencies and the relative photo yields of plastic scintillators 1421 (40 mm in diameter and 5 mm in thickness) are determined in the neutron energy range of 0.655—5 MeV.     

基于Micromegas探测技术的中子CT可行性研究(英文)

在培育新品种过程中能够实时掌握了解土壤中植物根系的形态以及其生长情况将为植物学家提供很多不可或缺的信息。对基于 micromegas 探测技术的中子 CT 在这一新应用的试验环境进行了仿真模拟, 通过三维图像重建后,得到了令人满意的预期结果。首先通过 Geant4 和 Garfield 模拟计算利用聚乙烯薄膜作为中子转换层的 micromegas 中子探测器, 得到了非常理想的位置分辨, 说明基于micromegas 探测技术建立中子 CT 照相系统的可行性。 然后利用MCNP仿真模拟14 MeV 中子CT 的实验环境, 最后由Matlab程序进行图像重建。In this paper, the possibility using micromegas(Micro Mesh Gaseous Structure) as neutron detector in 14 MeV neutron computed tomography(CT) has been simulated. The results show that the micromegas neutron detector has high spatial resolution and is a good candidate for neutron radiography. The three dimensional images of plant roots in soil are successfully and clearly obtained by the 14 MeV neutron CT with micromegas as a neutron detector. In the present simulation, MCNP is employed for 14 MeV neutron transport in the sample and Matlab for the 3 D photograph reconstruction.     

用直接中子法测量（n, 2n）反应截面的实验方法研究

在中国原子能科学研究院HI-13 串列加速器上的非常规多探测器快中子飞行时间谱仪上,采用直接中子法测量了14.3 MeV 中子与169Tm作用的(n,2n) 反应截面。用蒙特卡罗方法模拟了次级中子的产生,以对实验数据进行中子注量率衰减、多次散射和有限几何修正,同时结合SUNF 方法得到的评价能谱,给出了(n,2n) 反应截面的实验测量结果。测量截面以中子弹性散射微分截面作为标准截面来归一,并用反冲质子望远镜测量n-p 反应的反冲质子,以监视中子注量率。用直接中子法测量得到的结果与评价数据进行了比较,讨论了采用这种方法测量(n,2n) 反应截面的可行性。(n,2n) reaction cross section from 169Tm at 14.3 MeV was measured with the direct emittedneutron coincidence detecting method, using abnormal fast neutron TOF spectrometer on the HI-13 Tandem Accelerator at CIAE. Monte-Carlo method was used to simulate the generation of secondary neutron and correct the experimental data considering neutron flux attenuation, multiple scattering and finite geometry correction. Combining with evaluated spectra given by SUNF program, the experimental measurement results of the (n,2n) reaction cross sections were given. Cross sections of measurements were normalized by using neutron elastic scattering differential cross section as a standard section, and a recoil proton telescope was used to measure recoiling proton from the n-p reaction to monitor neutron flux rate. After comparing the experimental results with evaluated data, the feasibility of the direct emitted-neutron coincidence detecting method is discussed.     

Study of neutron activation yields in spallation reaction of 400 MeV/u carbon on a thick lead target

The spallation-neutron yield was studied experimentally by bombarding a thick lead target with 400 MeV/u carbon beam. The data were obtained with the activation analysis method using foils of Au, Mn, Al, Fe and In. The yields of produced isotopes were deduced by analyzing the measured γ spectra of the irradiated foils. According to the isotopes yields, the spatial and energy distributions of the neutron field were discussed. The experimental results were compared with Monte Carlo simulations performed by the GEANT4+FLUKA code.     

中子活化分析在古陶瓷原料产地研究中的应用

介绍了用中子活化分析方法测量古陶瓷和仿古陶瓷中的微量元素,通过对这些测量数据进行模糊聚类分析 ,可以确定这些古陶瓷和仿古陶瓷的材料来源 ,寻找提高仿古陶瓷质量的途径.Trace-elements in ancient ceramics and imitative ancient ceramics were determined by neutron activation analysis (NAA). The NAA data are then analyzed by fuzzy cluster method and the trend cluster diagram is obtained.The raw material sources of ancient ceramics and imitative ancient ceramics are determined. The path for improving quality of imitative ancient ceramics is found.     

瞬发γ活化分析系统的建立

瞬发γ中子活化分析是重要的核分析方法之一,是H和B等轻元素的重要分析手段,近年来应用范围不断增加.概要介绍了瞬发γ中子活化分析的基本原理,重点介绍了中国原子能科学研究院重水研究堆热中子束瞬发γ中子活化分析实验装置以及50 keV－11 MeV的宽能区γ效率刻度方法.还应用瞬发γ中子活化分析分析了海底锰结核标准物质GSPN 3中11种元素,结果与标准值基本一致.Neutron induced prompt γ activation analysis(PGNAA),is one of the nuclear analytical method,which is a powerful tool for H,B,etc.undestructive determination.The applications of PGNAA are increased in recent years.In this paper,the basic principle of PGNAA was introduced briefly.The facilities of PGNAA in HWRR of China Institute of Atomic Energy as well as the efficiency calibration for a wide range gamma from 50 keV to 10 MeV were emphasized.A deep sea polymetallic nodule CRM,GSPN 3 was analyzed by using PGNAA in this work,the results have agreement with the certified values.     

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.     

检查隐藏爆炸物的快中子分析方法

讨论了快中子分析检查隐藏爆炸物的原理，特点，主要技术关键和研究进展。     

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.     

中子活化分析原理及应用简介

介绍了中子活化分析的基本原理,详细给出中子活化方程的推导过程．概述其主要特点．通过实例对其应用进行了说明。     

活化法测量中子活化在线分析系统样品处的中子能谱

用多箔活化法测定了由Am Be中子源慢化屏蔽系统构成的中子活化在线分析系统样品处的中子能谱。 根据待测场点的中子注量率水平, 选用了5种非裂变核材料箔, 其中4种是中能区和热区的, 1种是快区的, 给出了各箔片的特性参数。 通过在待测场点对箔片进行辐照, 并测量其生成放射性核的γ放射性, 计算出了各箔片的活化率。 运用SAND II和MSIT迭代方法, 解出了待测场点的中子能谱。 详细分析了数据处理过程中群截面的加工处理以及由于自屏蔽效应引起的群截面修正问题; 研究了影响解谱精度的主要因素; 对解谱结果作了一定的分析讨论; 并用蒙特卡罗(MC)方法对最后的中子能谱做了不确定度分析。     

探测系统能量分辨在中子能谱数值模拟中的应用

针对中子能谱实验的数值模拟研究中涉及到的探测系统能量分辨问题,基于系统探测伽玛和中子的对应关系以及对伽玛射线的能量分辨率,介绍了一种简便实用的数值模拟方案,利用探测系统对中子、伽玛的光响应对应关系以及其对伽玛的能量分辨率,得到系统对中子的能量分辨率,再进一步把它应用到中子能谱的数值模拟中,并对数值计算结果与相关实验数据进行比较分析。结果表明,该方法可以很好地应用于中子能谱的数值模拟研究。     

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。     

Study of the RPC-Gd as thermal neutron detector

The BESⅢ RPC with Gd coating as thermal neutron detector was designed and constructed. Three prototypes were built with different techniques of producing the gadolinium converter. The performance of the cosmic ray test, the signal and the radiation spectrum were discussed in this paper. Lastly, the efficiency of one prototype with the best performance for detecting the thermal neutron was tested as 8.7%.