Studies on Thermal Neutron Backscattered by Neutral Beam Injector Ducts in Concrete Shield

Experimental studies on the angular flux distributions of backscattered thermal neutrons by neutral beam injector ducts (NBID) in ilmenite concrete are performed. The neutron flux distributions have been measured at the end of the ducted assembly and perpendicular to the duct axis by means of Indium thermal detector. The experimental facility and the detector activity measurement techniques are described. Results concerning injector ducts with different diameters are graphically represented. Calculations to analyse the experimental results are given.     

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。     

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。     

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.     

Search for Albedo Tritium with PAMELA Experiment

Physics of Atomic Nuclei - Particles of albedo radiation are the particles born in interactions of primary cosmic rays penetrating inside Earth’s atmosphere and magnetosphere and the...     

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.     

Feasibility of the Precise Energy Calibration for Fast Neutron Spectrometers

Computational studies aimed at improving the accuracy of measurements performed using neutron generators with a tritium target were performed. A measurement design yielding an extremely narrow peak in the energy spectrum of DT neutrons was found. The presence of such a peak establishes the conditions for precise energy calibration of fast-neutron spectrometers.     

中能中子与208Pb反应的理论计算和分析

在中子与原子核Pb及其同位素反应的总截面,去弹性散射截面,弹性散射截面和弹性散射角分布的实验数据基础上,获得了入射中子能量从1—300MeV的一组普适中子与Pb及其同位素反应的光学模型势参数.应用光学模型,扭曲波玻恩近似理论,宽度涨落修正的Hauser-Feshbach理论,预平衡反应的激子模型和核内级联模型,计算和分析了中子与²⁴⁸Pb反应的所有截面、角分布和能谱.理论计算与实验数据进行了分析比较     

在屏蔽墙外用雷姆计测量高能中子的修正因子

考虑到穿过混凝土屏蔽墙后中子能谱相对变“硬”的效应和中子雷姆计的能量响应特性,计算了用10英寸直径单球雷姆计和标准A–B雷姆计在屏蔽墙外测量中能重离子反应出射高能中子剂量当量的修正因子.     

数值模拟快中子针孔成像系统的PSF

采用蒙特卡罗方法对中子针孔成像系统进行了点扩展函数（PSF）的模拟研究, 利用高斯拟合的数学方法分析比较了几种不同条件下该系统的PSF。 研究结果表明, 在偏离量较小时, 利用高斯拟合得到的中子针孔成像系统的PSF是可行的, 而采用挡板可以很显著地减少拟合误差和提高其空间分辨率。 The point spread function (PSF) of a pinhole imaging system for fast neutron has been studied through Monte Carlo method. The PSFs under different conditions have been obtained and analyzed by fitting the simulating data with Gauss function. As the results show, when the excursion is little, the PSF obtained by Gauss function fitting is feasible. A baffle will reduce the error and improve the spatial resolution remarkably.     

12C快中子辐射俘获反应中的共振现象

主要研究中子辐射俘获反应中的共振现象,利用DSD模型计算激发能量在5—25MeV能区的¹²C(n,γ0)反应截面与E_n=9MeV时的角分布.所考虑的反应机制包括复合核俘获、直接和半直接俘获、复弹性和非弹性散射道的辐射俘获.计算表明,矮共振的峰值在激发能量为13MeV处;巨共振的峰值位置在激发能量21MeV处.计算结果与实验符合较好.     

Modeling the Behavior of a MOS Transistor under Fast Neutron and Gamma Irradiation

A numerical model of trapping of the radiation-induced charge in the bulk and on the surface of the oxide layer of a MOS transistor has been developed. The model takes into account the generation of point defects under fast neutron irradiation. The volume and surface charges obtained by the numerical modeling have been used to calculate the drain—gate characteristic of the MOS transistor exposed to neutron irradiation in different doses and accompanying high-energy gamma-ray irradiation. To model the effect of neutron irradiation, different methods for estimating the rate of point defect generation in a two-component material (SiO2) have been developed. The simulated drain—gate characteristic is shown to agree well with the experimental data obtained at the concentration of hole traps and their capture cross sections lying within the published data for an unirradiated device after exposure to gamma rays from a 60Co gamma source and after irradiation with fast neutrons with an average energy of ∼1 MeV and accompanying gamma rays using a pool-type reactor.     

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.     

Theoretical Calculations and Analysis of n+208Pb Reaction for Intermediate Energy Neutron

Based on experimental data of total, nonelastic, elastic cross section and elastic scattering angular distributions for n+Pb reactions, a set of neutron optical model potential parameters is obtained in the region of incident neutron energy from 1—300 MeV. The cross sections, angular distributions and energy spectra are calculated and analyzed by optical model, distorted wave Born approximation theory, Hauser-Feshbach theory, exciton model and cascade mechanism inside nuclear. The results indicate that the cross sections can be given for n+ ²⁰⁸Pb reactions which are all in good agreement with experimental data.     

Neutron matter with a model interaction

An infinite system of neutrons interacting by a model pair potential is considered. We investigate a case when this potential is sufficiently strong attractive, so that its scattering length a tends to infinity, a . It appeared, that if the structure of the potential is simple enough, including no finite parameters, reliable evidences can be presented that such a system is completely unstable at any finite density. The incompressibility as a function of the density is negative, reaching zero value when the density tends to zero. If the potential contains a sufficiently strong repulsive core then the system possesses an equilibrium density. The main features of a theory describing such systems are considered. Received: 17 December 1999 / Accepted: 23 December 1999     

用于快中子探测的裂变电离室实验及模拟结果比较(英文)

本文报道了一种用于快中子测量的裂变电离室的实验及模拟结果对比,该电离室的裂变材料为238U,分别电镀在电离室的阳极和阴极。裂变电离室通常有三种工作模式:脉冲模式、均方电压模式和电流模式,从而在大动态范围内实现中子注量测量。我们利用252Cf中子源对工作在脉冲模式的裂变电离室效率进行了测量,同时为了评估均方电压模式和电流模式,测量了裂变电离室在不同气压下的脉冲幅度,并通过Geant4蒙特卡罗软件对裂变电离室的脉冲幅度进行了模拟。模拟可以解释实验结果,当工作气压是2.64×105 Pa时探测效率最高[（4.30±0.7）×10-7],且裂变碎片能谱清晰,表明裂变电离室可以工作在不同模式下。     

An Automatic Activation Analysis System (AAAS) with the Use of Fast Neutron Generator

The described system is designed for automatic activation analysis with 14 MeV neutrons. The automatization comprises all operations and time control of the activation cycle. There is a possibility of independent programming of the irradiation time, the decay timè and seven consecutive measuring periods in large range (3 sec to 80 min) by means of a special time control unit. The dispatch of containers with samples is done with a very simple pneumatic device. The design and effectivity of shieldings against fast neutrons are also described.     

Advantages of a Fast Reactor Core Surrounded by a Physically Thick Neutron Reflector Made of Lead-208

Physics of Atomic Nuclei - In the paper, the influence of replacement of natural lead with lead-208 as a coolant and fast reactor reflector on its neutron-physical parameters is considered. The...