Fabrication and performance evaluation of GaN thermal neutron detectors with bm^6LiF conversion

A GaN-based pin neutron detector with a 6LiF conversion layer was fabricated, and can be used to detect thermal neutrons. Measurement of the electrical characteristic of the GaN-based pin neutron detector showed that the reverse leakage current of the neutron detector was reduced significantly after deposition of a 6LiF conversion layer on the detector surface. The thermal neutrons used in this experiment were obtained from an 241Am-Be fast neutron source after being moderated by 100-mm-thick high-density polyethylene. The experimental results show that the detector with 16.9-μm thick 6LiF achieved a maximum neutron detection efficiency of 1.9% at a reverse bias of 0 V, which is less than the theoretical detection efficiency of 4.1% calculated for our GaN neutron detectors.

基于LabVIEW设计的RPC-Gd热中子探测器测试系统

在WinXP系统下,基于LabVIEW开发了RPC-Gd热中子探测器的性能测试系统。结合LabVIEW图形显示能力和仿真仪器面板功能,通过调用外部动态链接库机制,封装CAMAC的I/O接口命令为功能函数子VI系列,以此将各电子学插件编译为功能模块。根据不同实验的要求可对功能模块进行灵活选择和设置。测试系统具有开放性、可移植性,使用界面友好简易。

Study on the gamma rays and neutrons energy response optimization of a scintillating fiber detector for EAST with Geant4

A new scintillating fiber detector inside magnetic shielding tube was designed and assembled for use in the next round of fusion experiments in the experimental advanced superconducting tokamak to provide D–T neutron yield with time resolution.In this study,Geant4 simulations were used to obtain the pulse height spectra for ideal signals produced when detecting neutrons and gamma rays of multiple energies.One of the main sources of interference was found to be low-energy neutrons below 10–5 MeV,which can generate numerous secondary particles in the detector components,such as the magnetic shielding tube,leading to high-amplitude output signals.To address this issue,a compact thermal neutron shield containing a 1-mm Cd layer outside the magnetic shielding tube and a 5-mm inner Pb layer was specifically designed.Adverse effects on the measurement of fast neutrons and the shielding effect on gamma rays were considered.This can suppress the height of the signals caused by thermal neutrons to a level below the height corresponding to neutrons above 4 MeV because the yield of the latter is used for detector calibration.In addition,the detector has relatively flat sensitivity curves in the fast neutron region,with the intrinsic detection efficiencies(IDEs)of approximately 40%.For gamma rays with energies that are not too high(<8 MeV),the IDEs of the detector are only approximately 20%,whereas for gamma rays below 1 MeV,the response curve cuts off earlier in the low-energy region,which is beneficial for avoiding counting saturation and signal accumulation.

Experimental research on a THGEM-based thermal neutron detector

A new thermal neutron detector with a domestically produced THGEM （Thick Gas Electron Multiplier） was developed as an alternative to 3He to meet the needs of the next generation of neutron facilities. One type of Au-coated THGEM was designed specifically for neutron detection. A detector prototype has been developed and the preliminary experimental tests are presented, including the performance of the Au-coated THGEM working in At/CO2 gas mixtures and the neutron imaging test with 252 Cf source, which can provide the reference for experimental data for research in the future.

Analysis of Nuclear Track Parameters of CN-85 Detector Irradiated to Thermal Neutrons by Using MATLAB Program

CN-85 detector which covered with boric acid H3Bo3 pellete has been irradiated by thermal neutrons from (241Am-9Be) source with activity 12 Ci and neutron flux 105 n. cm-2. s-1. The irradiation times-TD for detector were 4 h, 8 h, 16 h and 24 h. The track detector has been etched with sodium hydroxide. After chemical etching of the irradiated CN-85 detector, the images have been taken from a digital camera connected to the optical microscope. Image processing for the output images has been performed using MATALB program, and these images were analyzed and we had found the following relations: a) The relation between summation of opened track or surface density for tracks (intensity-IT) varies with radius of opening (track radius-RT). b) The relation between the tracks number-NT varies with the tracks diameter-DT (in micrometer) and tracks area-AT. That analysis of image processing was obtained, and the track intensity-IT was decreased with increase of track radius-RT at all of the irradiation time-TD. And the track intensity-IT was increased with increasing irradiation time-TD (h) for different track radius-RT (0.4225, 0.845, 1.2675 and 1.69 μm). The study indicates the possibility of using the analysis of image processing to CN-85 detector for classification of α-particle emitters through limitation of radius of track-RT, in addition to the contribution of these techniques in preparation of nano-filters and nono-membrane in nanotechnology fields.

Determination the Effect of Gamma Radiation and Thermal Neutron on PM-355 Detector by Using FTIR Spectroscopy

The effect of gamma on nuclear track detector type PM-355 (at the dose range 200 to 1600 kGy) and thermal neutron (flux 105 n·cm-2·s-1) was calculated by using of two irradiation methods. First method (G + N) was an irradiation PM-355 detector by gamma radiation and then irradiation by thermal neutrons, and another method (N + G) was irradiated by thermal neutrons and then gamma radiation. FTIR-spectroscopy was used to measure the change in deferent of transmission percent ΔT% at the wavenumber 1260 cm-1 with wavenumber 2962 cm-1 [ΔT%]1260-2962 and wavenumber 1138 cm-1 [ΔT%]1260-1138. The values of [ΔT%]1260-2962 and [ΔT%]1260-1138 were increasing with the increase of gamma irradiation with maximum response at 820 kGy and then drop after this dose until to 1600 kGy. This study determined the linear equations relation between the effect of gamma radiation on PM-355 detector and the change of [ΔT%]1260-2962 and [ΔT%]1260-1138, and this change appeared in (N + G) irradiation method better than in (G + N) irradiation method. The appearance of wavenumber 2964 cm-1 in (G + N) irradiation method referred to alkyl asymmetry C-H bond stretched out of skelated plane after changes in chemical structure of PM-355 detector by gamma or neutrons radiation.

Calculation of thermal neutron albedo for mono-material and bi-material reflectors

Thermal neutron albedo has been investigated for different thicknesses of mono-material and bi-material reflectors. An equation has been obtained for a bi-material reflector by considering the neutron diffusion equation. The bi-material reflector consists of binary combinations of water, graphite, lead, and polyethylene. An experimental measurement of thermal neutron albedo has also been conducted for mono-material and bi-material reflectors by using a^(241) Am–Be(5.2 Ci) neutron source and a BF3 detector. The maximum value of thermal neutron albedo was obtained for a polyethylene–water combination(0.95 ± 0.02).

Determining absolute value of thermal neutron flux density based on monocrystalline silicon in nuclear reactors

A new type of neutron detector based on monocrystalline Si is developed to measure the fluence and flux density of thermal and fast neutrons.The principle of this detector is based on the relationship between changes in electrical conductivity and neutron fluence during irradiation.Therefore,the absolute values of thermal neutron fluence and flux density are measured in a facile manner with high reliability.Compared with activation methods,our method not only possesses a similar accuracy,but also demonstrates superior application potential for the investigation of neutron fields in nuclear reactors owing to its suitable half-life.

中子多芯硼管探测器热中子灵敏度检测研究

中子探测器用于测量未知中子辐射场的中子信息时,热中子灵敏度是中子探测器的一项重要参数,需提前对其进行热中子灵敏度的检测,以保证数据的可靠性。此外热中子灵敏度也是中子探测器性能优劣的一个重要指标,指导着探测器的改进和应用。为检测某中子多芯硼管探测器样件的热中子灵敏度,提出一种在非标准中子场下测量热中子灵敏度的实验方法。该方法通过慢化同位素中子源建立含有热中子的中子场,利用活化箔法对探测器所在空间处的热中子注量率进行绝对测量,进而求得该中子探测器的热中子灵敏度。此外,对于不同几何布置下该中子多芯硼管探测器的热中子灵敏度检测结果进行实验分析,确定优选的几何布置。结果表明:该中子多芯硼管具有良好的热中子灵敏度,且测量结果与厂家在标定的结果吻合良好,验证该热中子灵敏度检测方法的可行性与准确性。此实验方法为后续开展探测器的结构设计、优化等提供便利。

Measurement of the Energy Spectrum of the Neutrons inside the Neutron Flux Trap Assembled in the Center of the Reactor Core IPEN/MB-01

This paper presents the neutron energy spectrum in the central position of a neutron flux trap assembled in the core center of the research nuclear reactor IPEN/MB-01, obtained by an unfolding method. To this end, we have used several different types of activation foils （Au, Sc, Ti, Ni, and plates） which have been irradiated in the central position of the reactor core （setting number 203） at a reactor power level （64.57±2.91 watts）. The activation foils were counted by solid-state detector HPGe （high pure germanium detector） （gamma spectrometry）. The experimental data of nuclear reaction rates （saturated activity per target nucleus） and a neutron spectrum estimated by a reactor physics computer code are the main input data to get the most suitable neutron spectrum in the irradiation position obtained through SANDBP （spectrum analysis neutron detection code-version Budapest University） code： a neutron spectra unfolding code that uses an iterative adjustment method. the integral neutron flux, （2.41 ± 0.01） × 10^9 n·cm^-2·s^-1 for the thermal The adjustment resulted in （3.85 ± 0.14） × 10^9 n·cm^-2·s^-1 for neutron flux, （1.09 ±0.02） × 10^9n·cm^-2·s^-1 for intermediate neutron flux and （3.41 ± 0.02） × 10^8 n·cm^-2·s^-1 for the fast neutrons flux. These results can be used to verify and validate the nuclear reactor codes and its associated nuclear data libraries, besides, show how much effective it can be that the use of a neutron flux trap in the nuclear reactor core to increase the thermal neutron flux without increase the operation reactor power level. The thermal neutral flux increased 4.04 ± 0.21 times compared with the standard configuration of the reactor core.

变组分变掺杂p-i-n型AlGaAs/GaAs微结构中子探测器性能表征

制备了一种在p-i-n型AlGaAs/GaAs材料上刻蚀微沟槽的中子探测器。通过MOCVD技术生长了变组分变掺杂的p-i-n型AlGaAs/GaAs,使用ICP技术在材料上刻出微沟槽,沟槽宽度为25μm,深度为10μm。探测器的探测面积为4 mm^(2),沟槽宽度和间距为1∶1,呈周期性排列,在沟槽中填充中子转换材料探测热中子信号。通过对平面和微结构p-i-n型AlGaAs/GaAs探测器的电学特性、α粒子以及中子探测性能的比较分析,发现两者在电学特性和α粒子能量分辨率方面有较大差别。5 V偏压下平面型和微结构AlGaAs/GaAs探测器的漏电流分别是-0.024 1μA、-0.627μA,两者相差近30倍,这是由于微结构刻蚀了部分异质结导致器件表面漏电流增加。0 V偏压下微结构探测器α粒子能量分辨率比平面型也有些许恶化,但在热中子探测上微结构效果更佳,中子总计数微结构比平面型多一倍。微结构降低了探测器的自吸收问题,同时增大了探测器的中子接触面积,在热中子探测上应用前景广阔。

掠入射涂硼多丝正比室中子探测器设计及其性能模拟

针对国内中子散射谱仪对高效率高位置分辨的热中子探测器需求,对基于多层掠入射涂硼多丝室的新型位置灵敏中子探测器进行了模拟研究。利用蒙特卡洛模拟软件Geant4对探测器的中子探测效率、位置分辨率以及基材对中子的散射进行了模拟仿真。结果表明,采用掠入射多层结构可以实现较高的中子探测效率和位置分辨率。当掠入射角度为5°时,采用3层结构可以对波长2.5 A的热中子实现62%的探测效率;对于2 mm的阳极丝间距,掠入射结构下探测器的位置分辨(FWHM)可达0.286 mm。

用于中国散裂中子源闪烁体中子探测器的^(6)LiF/ZnS(Ag)闪烁屏性能研究

^(6)LiF/ZnS(Ag)闪烁屏是闪烁体型中子探测器的重要组成部分,其性能优劣会直接影响着探测器的应用,为了筛选出满足中国散裂中子源(CSNS)上工程材料中子衍射谱仪和能量分辨中子成像谱仪的中子探测器需求的高性能闪烁屏,利用中国散裂中子源的20号中子束线,系统研究了AST公司的多种^(6)LiF/ZnS(Ag)闪烁屏样品的相对热中子探测效率和中子信号积分谱,并通过刻度光测试系统中的光电倍增管得到这些样品的出射光产额,选取出用于闪烁体中子探测器的最佳闪烁屏材料。研究结果表明,^(6)LiF∶ZnS(Ag)质量分数比为1∶2,基底材料为塑料,闪烁屏厚度为300μm的AST-26139闪烁体样品性能较高,满足中子谱仪的中子探测器需求。

中子探测用LiInSe_(2)晶体生长及表征

LiInSe_(2)晶体是一种可在室温下探测热中子的新型半导体中子探测材料。本文采用低温合成法,获得大量高纯多晶LiInSe_(2)原料,通过改进生长工艺得到了高质量的红色LiInSe_(2)晶体。通过研究晶体的透过率、夹杂相等,表征了晶体的生长质量,测试晶体对α粒子的响应来研究晶体进行中子探测的可能性。结果表明,晶体的红外透过率为75%,禁带宽度为2.3 eV,夹杂相密度达到2 900个/cm^(2),夹杂相的尺寸在1~10μm左右。测得电阻率在5×10^(11)Ω·cm左右,对α粒子的能量分辨率为55%。

用于热中子探测的正比管性能研究

简要对最常用的三种正比管的热中子探测效率及灵敏度进行了实验比较,还给出了一维3He位置灵敏热中子探测器的初步实验研究结果。

基于~6LiF/ZnS（Ag）闪烁体波移光纤读出中子探测器模拟研究

利用GEANT4构建二维位置灵敏型闪烁体中子探测器模型,并对探测器的关键性能进行了系统的模拟研究.计算结果表明,采用双层闪烁屏与波移光纤作为夹层的"三明治"式结构探测器,其热中子探测效率可以达到49.1%.模拟和实验均表明:探测器具有较好的n/γ抑制能力,γ灵敏度小于10-5;中子位置分辨率随着光纤芯间距和光纤与闪烁屏距离的减小呈现减小趋势,本征空间分辨率最好可以达到X轴0.08mm,Y轴0.12mm;光纤与闪烁屏之间采用空气耦合位置分辨率好于硅油耦合.模拟结果与部分实验结果的对比验证显示,探测器具有较好的二维成像能力.

热中子分析探雷技术的实验研究

为验证热中子分析(Thermal neutron analysis,TNA)方法用于地雷探测的可行性,探索并掌握该方法的技术特点。采用国产新型LaBr3(Ce)快闪烁体探测器,搭建了一套基于252Cf同位素中子源的热中子分析探雷实验系统,主要包含慢热中子转化系统、屏蔽系统、探测系统三个部分。在此基础上,研究了宽能量范围特别是对高能段的精确刻度方法,提出了基于N(H)元素10.83 MeV(2.22 MeV)特征信号计数异常的地雷最小可探测时间。在黄土、粘土、沙土以及磁性土的实验雷池中对72式反坦克地雷、500 g TNT样品以及多种干扰物进行了测试。结果表明,该套探雷实验系统可实现不同背景下的地雷探测,并能有效判弃传统探雷技术易产生虚警的干扰物。

核径迹热释中子探测器测量高中子通量密度

本文提出一种用于高中子通量密度测量的方法,即使用核径迹热释中子探测器测量中子通量密度,该方法在低中子通量密度测量方面已成功在微型中子源反应堆上得到验证。为了测试其在高中子通量密度测量方面的适用性,在中国先进研究堆辐照孔道内进行了应用研究。结果表明:孔道内中子通量密度相对分布总体趋势与MCNP的计算结果符合较好,此种方法测量高中子通量密度有效可行。

涂硼MRPC热中子探测器用于补偿中子测井的蒙特卡罗研究

本文利用蒙特卡罗方法模拟了涂硼多气隙电阻板室(Multi-gap Resistive Plate Chamber,MRPC)热中子探测器和3He正比计数管在常规条件和欠平衡条件下的补偿中子测井中的响应。模拟结果表明,使用涂硼MRPC热中子探测器时,得到近远探测器计数随孔隙度而增加,且与使用3He正比计数管时得到的结果基本一致,说明涂硼MRPC热中子探测器可用于补偿中子测井。

Garfield模拟工作气体对涂硼MRPC热中子探测器性能的影响

多气隙电阻板室(Multi-gap Resistive Plate Chamber,MRPC)是一种新型气体探测器,具有探测效率高和时间分辨好等优点,在内层玻璃涂硼后可用于热中子探测。不同的工作气体对涂硼MRPC热中子探测器的性能有很大影响。利用Garfield模拟了不同工作气体的汤生系数η、电子吸附系数α、漂移速度v、扩散系数D等物理参数,并计算给出了MRPC的时间分辨率σt、本征探测效率ε。通过模拟结果对工作气体进行优化,为探测器的实际制作和实验测试提供必要的指导。