可用于激光核聚变的闪烁中子探测器

在当前激光核聚变实验中,中子集中在短时间内出现、且产额低。为适应这种特点,要求探测器的效率高,分辨时间短。利用闪烁中子探测器探测激光核聚变所产生的中子,能测定中子产额,记录中子能量,而且探测效率高,分辨时间短。缺点是易受γ射线、X射线的干扰。     

液体闪烁体探测器测量皮秒激光脉冲中子源能谱

在星光Ⅲ实验装置上开展皮秒激光脉冲中子源实验,使用液体闪烁体探测器测得较好的中子信号,利用飞行时间法获得中子的能量/时间分布,通过示波器电压时间积分与阻抗之比得到不同能量段的电荷值。建立液体闪烁体探测器Geant4计算模型,通过实际打靶情况与标定情况下液体闪烁体探测器出光口收集到的可见光光子数之比,结合标定的灵敏度数据,获得液体闪烁体探测器对不同能量中子的灵敏度。计算得到源发射的中子能谱,能量在1 MeV以上的液体闪烁体探测器方向测得的中子产额为1.04108 sr-1。     

超快中子探测器闪烁体性能计算

超快中子探测器是ICF聚变反应速率测量系统的核心部件。利用蒙特卡罗粒子输运工具包Geant4模拟了一种超快中子探测器——BC-422型闪烁探测器的中子探测过程,计算出了几种厚度的BC-422型闪烁体的探测效率、输出光信号强度和时间分辨力;对比了闪烁体的2种不同反射表面对输出光信号强度和时间分辨力的影响。计算的结果显示:设计适当的BC-422型闪烁探测器能够测量的最低中子产额在108量级,对DT中子的信号时间分辨力好于20 ps,对DD中子的信号时间分辨力达到30 ps,能够用于大型激光装置及其原型的聚变反应速率测量。     

用于DPF装置中子测量的闪烁体探测器

 介绍了一种用于等离子体焦点装置(DPF装置)中子波形测量的塑料闪烁体探测器,该探测器由ST401型塑料闪烁体、XP2262B型光电倍增管构成。利用银活化中子探测器和DPF装置对该塑料闪烁体探测器进行标定,确定其中子灵敏度为0.022 5 pC每中子,,中子产额测量范围达到10⁹～10¹¹每脉冲,可以满足DPF装置中子参数测量的需要。     

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.     

一个宽范围能响平坦的长中子计数器

由于对γ射线灵敏度低，而且可在很宽的范围内中子能量响应比较平坦，长计数管在中子产额的测量中得到了广泛的应用。为了提高探测效率，一般用BF3或^3He正比管外包围一定厚度的石蜡或聚乙烯慢化体来构成长计数管探测系统。建立的长计数器主要是针对中子管产生的DD（2．4MeV）或DT（14．1MeV）或两种能量混合的脉冲中子进行测量。为了达到探测系统设计要求，首先详细模拟了慢化体尺寸及结构对探测效率的影响，以便对探测器系统的加工制作提供依据。根据模拟结果建立了探测器，从实验上对探测器的性能进行了测量。     

新型热中子敏感微通道板探测效率的蒙特-卡罗模拟研究

基于microchannel plates (MCP)的中子探测技术近年来发展迅速, 因其具有较高的空间分辨率和中子探测效率以及优异的时间分辨能力, 可用于高分辨率中子照相和能量选择中子成像. 本文利用蒙特-卡罗(MC)程序, 对栅格为15 μm的热中子敏感MCP板进行MC模拟计算, 获得了不同几何结构和材料组成情况下, 掺杂型和镀膜型热中子敏感MCP板的探测效率. 计算结果表明, 增加中子敏感材料的比例可以获得更高的中子阻挡效率, 但同时也加大了次级粒子发射进入MCP板通道的难度, 掺杂型MCP 板的通道直径和镀膜型MCP板的镀膜厚度均存在最优值. MCP板厚度为0.4 mm时, 对¹⁰B₂O₃材料, 掺杂型MCP板的热中子探测效率可以超过40%, 镀膜型MCP板的热中子探测效率可以接近60%.     

ICF中子产额测量中统计涨落分析及计算

 塑料闪烁探测器通常用来测量氘氘、氘氚聚变中子产额。中子在闪烁体中产生的质子数的统计涨落及质子在闪烁体中沉积能量的统计涨落为测量结果引入了两项不确定度分量。以氘氚聚变中子为例,分析了这两种统计涨落的概率密度函数的计算方法,该计算方法也适用于其它能量的单能快中子和塑料闪烁体作用的相应计算。     

溴化镧闪烁体探测器性能及应用研究

LaBr3(Ce)探测器是一种新型闪烁体探测器,具有高光产额,高探测效率,高时间和空间分辨率,高能量分辨率,温度特性良好,抗辐射性能良好,操作简便等优点.从2001年以来,该探测器得到了迅速的研究和应用.LaBr3(Ce)探测器在核共振荧光检测、瞬发γ中子活化分析、爆炸物检测、核医学成像、环境辐射监测、空间辐射探测等方面的应用研究中取得了非常良好的效果.该探测器表现出优于以往用于这些领域的探测器的性能(例如NaI(Tl)探测器、BGO探测器、HPGe探测器等).介绍了LaBr3(Ce)探测器的性能及其应用研究进展,对代表性文献进行了简析和综述,阐明了其良好的应用前景.     

溴化镧闪烁体探测器性能及应用研究（英文）

LaBr3(Ce)探测器是一种新型闪烁体探测器,具有高光产额,高探测效率,高时间和空间分辨率,高能量分辨率,温度特性良好,抗辐射性能良好,操作简便等优点。从2001年以来,该探测器得到了迅速的研究和应用。LaBr3(Ce)探测器在核共振荧光检测、瞬发γ中子活化分析、爆炸物检测、核医学成像、环境辐射监测、空间辐射探测等方面的应用研究中取得了非常良好的效果。该探测器表现出优于以往用于这些领域的探测器的性能(例如NaI(Tl)探测器、BGO探测器、HPGe探测器等)。介绍了LaBr3(Ce)探测器的性能及其应用研究进展,对代表性文献进行了简析和综述,阐明了其良好的应用前景。     

A study of ZnS(Ag)/6LiF with different mass ratios

The properties of ZnS(Ag)/⁶LiF samples with three different mass ratios were studied. The study showed that the EJ426 sample with the mass ratio of 3:1 had the highest detection efficiency of thermal neutrons, which was 32.4% in the experiment. Furthermore, this sample had the largest charge spectrum. The light yield of its surface at the average value of the charge spectrum was approximately 8.01 × 10³ photons/neutron. The gamma sensitivity of the sample was better than 10⁻⁶ at the threshold of 350 photoelectrons. Therefore, EJ426 is a good candidate for a position-sensitive thermal neutron detector.     

Detection efficiency evaluation for a large area neutron sensitive microchannel plate detector

In this paper, the detection efficiency of a large area neutron sensitive microchannel plate detector has been evaluated. A ~6LiF/ZnS scintillator detector 65 mm in diameter and 0.32 mm in thickness, with product code,EJ426HD2, produced by Eljen Technology, was employed as the benchmark detector. The TOF spectra of these two detectors were simultaneously measured and the energy spectra were then deduced to calculate the detection efficiency curve of thenMCP detector. Tests show the detection efficiency@25.3 me V thermal neutrons is 34% for this ~nMCP detector.     

The Monte-Carlo simulation on a scintillator neutron detector

A simulation of the properties of the shifting scintillator neutron detector using 6LiF/ZnS(Ag) scintillation screens is performed.The simulation results show that the light attenuation length of standard BC704 scintillator is about 0.65 mm.Its thermal neutron detection efficiency,gamma sensitivity and intrinsic spatial resolution can achieve around 50.0%,10 5and 0.18 mm(along X-axis) respectively.For the detector,air coupling position resolution is better than the silicone oil coupling.Some of the simulation results are compared with experimental results.They are in agreement.This work will be helpful for constructing neutron detector for high intensity powder diffractometer at Chinese spallation neutron source.     

Characteristics of a stilbene scintillation crystal in a neutron spectrometer

Various organic scintillators are commonly used as the detecting material for neutrons, but these detectors are less sensitive to gamma rays. In particular, stilbene crystals and BC501A (NE213, EJ301) have good pulse-shape discrimination (PSD) between neutron and gamma-ray events, and have been selected as the media for fast-neutron detection among the organic, inorganic and plastic materials in a mixed radiation field. Although some of the scintillation characteristics of stilbene crystals have been studied, the detailed scintillation characteristics of the crystal are not completely understood. In this study, the light yield, decay time and pulse shape discrimination capability of a stilbene crystal were measured because this crystal is an optimized detector in a large flux of neutrons such as those might be found in cyclotron and charged particle accelerator facilities. The pulse-shape discrimination of neutrons and gamma rays with a stilbene crystal was measured using a ²⁵²Cf neutron source at room temperature. A neutron tagger module was used for the neutron and gamma separation using the charge comparison method in real time. The total pulse width for the charge integration and the delay from the peak-to tail start time were optimized for a better neutron and gamma separation. The relative light yield and decay time of the stilbene crystal scintillator were also measured.     

A capture-gated fast neutron detection method

To address the problem of the shortage of neutron detectors used in radiation portal monitors(RPMs),caused by the ~3He supply crisis, research on a cadmium-based capture-gated fast neutron detector is presented in this paper. The detector is composed of many 1 cm × 1 cm × 20 cm plastic scintillator cuboids covered by 0.1 mm thick film of cadmium. The detector uses cadmium to absorb thermal neutrons and produce capture γ-rays to indicate the detection of neutrons, and uses plastic scintillator to moderate neutrons and register γ-rays. This design removes the volume competing relationship in traditional ~3He counter-based fast neutron detectors, which hinders enhancement of the neutron detection efficiency. Detection efficiency of 21.66% ± 1.22% has been achieved with a 40.4 cm × 40.4cm × 20 cm overall detector volume. This detector can measure both neutrons and γ-rays simultaneously. A small detector(20.2 cm × 20.2 cm × 20 cm) demonstrated a 3.3 % false alarm rate for a ~(252)Cf source with a neutron yield of 1841 n/s from 50 cm away within 15 s measurement time. It also demonstrated a very low(0.06%) false alarm rate for a 3.21 × 10~5 Bq ~(137)Cs source. This detector offers a potential single-detector replacement for both neutron and the γ-ray detectors in RPM systems.     

用于神光Ⅲ燃料面密度诊断的下散射中子探测系统设计

根据辐射屏蔽后5.5m测点处的辐射场情况,分别设计了电流型探测器系统和成像型探测器系统。通过Geant4数值模拟分析可得:在面密度达到10mg/cm2、初级中子产额为1012时,电流型探测器系统满足测量的信噪比,信噪比达到40∶1;在面密度达到10mg/cm2、初级中子产额为1011时,成像型探测器系统满足测量的信噪比,信噪比好于10∶1;面密度增大时,信噪比有所改善;但是当初级中子产额达到1012时,出现中子信号重叠现象,可通过缩短曝光时间或者减小塑料闪烁体厚度来降低中子重叠率。     

血液中Na活化放射性测量的蒙特卡罗模拟

针对超临界事故中人体受到中子辐照后感生的24Na活度测量,采用MCNP软件建立蒙特卡罗模拟模型,分别模拟不同类型NaI探测器对24Na衰变的两条射线全能峰的探测效率和塑料闪烁体探测器对24Na衰变的射线总计数的探测器效率。模拟结果表明:井型NaI探测器与圆柱型相比,24Na衰变的1.38 MeV和2.76 MeV 射线全能峰探测效率分别提高了4.30倍和4.11倍;塑料闪烁体探测器对24Na衰变的射线的探测效率是NaI探测器对24Na 射线的探测效率的1.72倍;同时粗略计算了探测器计数与人体所受中子辐照剂量之间的关系。