塑料闪烁探测器测量辐射驱动内爆的中子产额

本文介绍了在ＬＦ－１２装置上，用塑料闪烁探测器诊断辐射驱动内爆低产额中子的过程，并讨论了中子产额与靶型及靶参数的关系。结果表明，在ＬＦ－１２装置上，对不同的靶，激光辐射驱动内爆的中子产额为１０＾３－１０＾５。     

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。     

n-r分辨应用于^252Cf自发裂变中子飞行时间谱测量

飞行时间法是精确测量快中子能谱的有效方法。但是在实际应用中，各种中子灵敏探测器同时也对r射线灵敏，中子源的伴随r射线会直接影响中子能谱的求解精度。液体闪烁体BC501具有良好的时间响应特性和n-r分辨本领，广泛适用于r射线场中的快中子参数测量。文中选用液体闪烁体BC501作为快中子探测器，根据中子和丫射线在液体闪烁体中产生的闪烁光退光时间长短的明显差异，应用脉冲上升时间法进行n-r分辨，通过对符合甄别^252Cf自发裂变中子飞行时间谱中的丫射线的效果进行研究，从应用的角度描述了脉冲上升时间法的n-r分辨效果。     

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。     

ST401塑料闪烁体中子、r灵敏度测量

ST401塑料闪烁体响应时间快，在脉冲中子源方法测量瞬发中子衰减常数中常用作中子探测器，同时它对于r射线也灵敏。利用加速器DT中子源、裂变谱中子源和^60Co同位素源，分别测量了三种尺寸的ST401塑料闪烁体的裂变谱中子和r射线的灵敏度。     

Be(d,n)反应中子源能谱测量及应用

 利用中子飞行时间技术和BC501A液体闪烁探测器的粒子分辨特性,测量了0°方向、20 MeV氘束轰击厚金属铍靶反应产生的中子源能谱,测量的中子能谱范围为0.7～25.0 MeV。在60°方向放置芪晶体闪烁探测器,由刻度好的BC501A液体闪烁探测器归一校正后,用于中子源强度监测。利用Be(d, n) 反应中子源,采用单粒子灵敏度标定方法,实验标定了0.75~15.75 MeV能量范围内的薄膜闪烁探测器中子能量响应曲线,实验结果与蒙特卡罗模拟计算结果在8%的不确定度范围内一致。     

一种基于~4He气闪烁体的裂变中子探测器

研制了一种新中子探测器,它以²³⁵UO₂裂变靶作为转换靶,⁴He气体作为闪烁体.该探测器充分结合了²³⁵U和⁴He两种核素的特点,从而具有中子能量响应平坦、中子灵敏度较高、n/γ分辨本领高等优点,能很好地在混合脉冲裂变辐射场中测量中子.本文对探测器的原理和结构设计进行了介绍,计算了不同能量中子、γ射线在探测器中的能量沉积,并从理论和实验上对探测器的中子灵敏度、γ射线灵敏度、n/γ分辨本领和时间响应进行了研究.结果表明探测器的中子灵敏度约10^-15C·cm²,γ灵敏度约10^-17C·cm²,时间响应约33.1 ns.     

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。     

基于纯冲击波聚心的准一维氘氘内爆物理实验

在神光Ⅲ原型装置上利用八路6400J/1ns激光注入1100μm×1850μm的黑腔内产生210eV的高温辐射场,均匀辐照填充氘氘燃料的靶丸实现内爆。实验中选择高气压薄壳靶丸实现纯冲击波聚心内爆。通过闪烁体探测器、中子条纹相机等多套诊断设备获取了中子产额、聚变反应时刻等关键内爆参数。结合一维数值模拟表明,实验测量的中子产额与干净一维数值模拟计算的中子产额之比达到90%;同时通过人为破坏内爆对称性等方式表明,该设计下内爆中子产生机制集中于冲击波聚心,其内爆性能受到高维因素影响极低,从而实现了准一维内爆。     

塑料闪烁探测器氘氚中子灵敏度标定

为了测量ＬＦ－１２装置激光聚变Ｄ－Ｔ中子产额，我们通过ＮＳ－２００加速器和脉冲中子管对实验所用几个塑料闪烁探测器的Ｄ－Ｔ中子灵敏度进行了标定，给出了各探测器在不同条件下的Ｄ－Ｔ中子灵敏度值。加速器和脉冲中子管两种方法的测量误差分别为±１３％和±５０％，两种标定结果在误差范围内是一致的。     

应用于热中子的nTHGEM探测器性能研究

随着脉冲强流中子源的发展,对高性能中子探测器提出了更大的挑战,3He气体资源严重短缺和高计数率中子探测器的迫切需求,已开始制约着中子源应用技术的发展。中国科学院高能物理研究所针对中子的特殊性,专门研发了一种陶瓷基材的nTHGEM（neutron Thick Gaseous Electron Multiplier）探测器用于中子探测。基于nTHGEM的中子探测器具有高计数率、高位置与时间分辨能力、增益大、制作工艺简单,且便于大面积制作的特点,是目前国际上发展替代3He探测技术的重要方向之一。为了详细研究nTHGEM探测器的本身性能,本工作使用55Fe放射源研究了nTHGEM探测器的增益、计数率稳定性、能量分辨率等关键参数与nTHGEM膜间电压、收集场强、漂移场强之间的关系,优化了nTHGEM探测器在不同工作气体中的工作参数,为后续进一步优化nTHGEM探测器设计和工艺奠定了基础。实验结果表明,单层nTHGEM探测器在Ar（90%）+CO₂（10%）混合气体中增益能达到103,探测器计数率稳定性良好。另外,还在中国原子能科学研究院的CARR反应堆（China Advanced Research Reactor）上进行了中子束流实验,通过狭缝测量到探测器位置分辨率为（3.01±0.03）mm（FWHM）,已经接近高气压3He MWPC中子探测器水平。With the development of pulsed intense neutron source, the high-performance neutron detector poses more challenges. The severe shortage of 3He gas resources and the urgent need of neutron detector with high counting rate have begun to restrict the neutron source application technology development. In response to the particularity of neutrons, the Institute of High Energy Physics of CAS developed a nTHGEM(neutron Thick Gaseous Electron Multiplier)of ceramic substrate for neutron detection. The neutron detector based on nTHGEM is one of the most important directions for the development of alternative 3He detection technology in the world at present because of its high counting rate, high position and time resolution, large gain, simple fabrication process and large area production. In order to study the properties of nTHGEM detector in detail, this paper studied the relationship between nTHGEM detector's gain, counting rate stability, energy resolution and other key parameters and nTHGEM film voltage, collection field strength and drift field strength using 55Fe radioactive source, Optimized the working parameters of nTHGEM detector in different working gases, which laid the foundation for further optimization of nTHGEM detector design and process. The experimental results show that the single-layer nTHGEM detector has a gain of 103 in a Ar(90%)+CO₂(10%) mixed gas with good counting rate stability. In addition, a neutron beam experiment was performed on the China Advanced Research Reactor at the China Institute of Atomic Energy, and the position resolution of the detector was (3.01±0.03) mm (FWHM) measured by slits. Its performance is close to the high pressure 3He MWPC neutron detector level.     

GaAs：Cr探测器中子辐照改性研究

介绍了一种新型脉冲辐射探测器以及提高其性能的一种方法,并报告了探测器性能与中子积分通量关系的实验结果。     

DT聚变脉冲中子产额的活化测量法

设计了一个测量高强度DT聚变脉冲中子产额的活化探测器.该探测器由中子慢化体、天然银片、塑料闪烁体和光电倍增管组成,其输出电流通过一个小电流计来获取.通过分析探测器在直流标定和脉冲测量两种状态下输出电流的变化曲线,求解出了特征参数,进而推导计算出DT聚变脉冲中子源的产额.实践证明,这种测量方法与传统的活化法相比,减少了对...     

介质型快中子探测器中子直照响应模拟研究

 介质型快中子探测器的中子直照响应对其设计和实际应用具有重要影响。利用Geant4编制Monte-Carlo模拟程序对此型探测器的中子直照响应进行了计算。模拟了探测器芯子常用材料在中子入射时带电重粒子的发射情况,发现电荷收集极、卡阈吸收片和后高压绝缘层材料的选择对中子直照响应特性有直接影响。在现有的以聚四氟乙烯为卡阈吸收片和后高压绝缘层材料的探测芯子中,直照响应给总的中子灵敏度带来约6%的贡献。提出了一种使用高电阻率石墨作为卡阈吸收片和后高压绝缘层材料的探测芯子的优化结构,可有效降低中子直照响应。     

氘氘中子产额铟活化诊断方法

提出了活化法测量DD中子产额的实验方法,该方法可提高DD中子产额测量的精度。方法基于铟同位素115In与DD中子的非弹性散射反应,活化反应释放的射线被HPGe探测器记录,根据活化系统标定灵敏度推算出中子产额。分析了探测器记录的活化射线数与中子产额间的关系。介绍了一套活化测量的系统设计。通过蒙特卡罗方法模拟了活化样品出射的射线数与样品厚度的关系,模拟结果表明:样品厚度取为1 cm可兼顾活化效率和测量精度。在加速器上对铟活化样品进行了标定实验,实验结果表明:在聚变中子产额大于2109的实验中可使用铟活化诊断方法,中子产额测量的相对标准误差在10%以内。随着聚变中子产额的不断提高,铟活化测量中子产额的精度可进一步提高。     

Study of a nTHGEM-based thermal neutron detector

With new generation neutron sources, traditional neutron detectors cannot satisfy the demands of the applications, especially under high flux. Furthermore, facing the global crisis in ~3He gas supply, research on new types of neutron detector as an alternative to ~3He is a research hotspot in the field of particle detection. GEM(Gaseous Electron Multiplier) neutron detectors have high counting rate, good spatial and time resolution, and could be one future direction of the development of neutron detectors. In this paper, the physical process of neutron detection is simulated with Geant 4 code, studying the relations between thermal conversion efficiency, boron thickness and number of boron layers. Due to the special characteristics of neutron detection, we have developed a novel type of special ceramic n THGEM(neutron THick GEM) for neutron detection. The performance of the n THGEM working in different Ar/CO_2 mixtures is presented, including measurements of the gain and the count rate plateau using a copper target X-ray source. A detector with a single n THGEM has been tested for 2-D imaging using a ~(252)Cf neutron source. The key parameters of the performance of the n THGEM detector have been obtained, providing necessary experimental data as a reference for further research on this detector.     

SiC基中子探测器对热中子的响应

以SiC二极管和中子转换材料6LiF为基础,研制了SiC基中子探测器,并用241Am源与临界装置分别研究了SiC基中子探测器的粒子响应、热中子响应。结果表明:SiC基中子探测器能够满足241Am源粒子的计数测量,但由于SiC二极管灵敏区薄,故不能用于5.48 MeV的粒子能谱测量;SiC基中子探测器对热中子响应良好,不同功率下,脉冲幅度谱中可清晰看到由6Li(n,)3H的反应产物粒子、3H粒子形成的双峰;脉冲幅度甄别法可将射线及电子学噪声甄别掉;在直接测量与符合测量中,SiC基中子探测器的计数率均与临界装置功率成线性关系,且直接测量的线性度比符合测量的线性度好,最好可达0.999 97。研究表明:降低肖特基接触金属的厚度、增加其外延层厚度、提高其外延层品质,可将SiC二极管用于带电粒子能谱测量。     

辐射防护仪表刻度

概述了中子和γ辐射防护仪表刻度地标准、要求、方法和误差．还扼要介绍了近物所中子、γ辐射防护仪表的刻度工作.The Calibration purposes, method, criterion , error analyses and requirement of radiation detector are briefly described. The calibration procedure for neutron and γ radiation detector at institute of Modern Physics are also introduced.     

Experimental neutron flux measurements with a diamond detector at the QUINTA setup

The operational capability of a diamond detector used to measure the neutron spectrum by the response function on the QUINTA setup [1] installed at the proton beam of the phasotron [2] (Laboratory of Nuclear Problems, Joint Institute for Nuclear Research) was demonstrated in the energy interval of 2.1–20 MeV. The neutron-flux count rate was measured. The energy of neutrons was estimated at 7.4–25.7 MeV based on the diamond-detector response spectrum. The dependence of the diamond-detector response spectra on the angle between the proton beam and the line going through the detector and the center of the QUINTA setup was investigated. The angular anisotropy of the neutron flux was demonstrated. Measurements at different distances from the detector to the QUINTA setup were performed.     

Neutron field mapping and dosimetry by CR-39 for radiography and other applications

A neutron telescope based on the n–p elastic scattering on H is suggested to investigate the inhomogeneity of neutron fields used for different applications like neutron radiography, biological investigations or dosimetry where the number of neutrons with high energy (above 8 MeV) is negligible. The telescope consists of a thin polyethylene foil and a track etch detector divided by an air gap and placed inside a glass tube which can be evacuated by a simple vacuum pump. The angular and energy resolution of the telescope mostly depend on the diameter of the tube, the length and pressure of the air gap, on the thickness and H content of the radiator and on the type of the track detector. The response of the telescope is characterized by several parameters: the incident angle distribution of protons, the length and the minor diameter distributions of the etched tracks. The response was calculated for several assemblies by a Monte Carlo code and based on the results, three different experimental telescopes were constructed and tested. The most suitable one was selected for routine measurements.