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。     

面向脉冲星导航的聚焦型X射线探测器测试标定方法研究

通过脉冲星辐射信号特征研究和空间观测需求分析,提出了一种面向导航应用的X射线探测器测试方法.首先推导了X射线光子欠探测概率公式,分析了不同星源流量及不同探测器时间分辨率下对光子探测能力的影响.通过数值模拟方法建立了脉冲到达时间与脉冲轮廓相似度的关系.处理了我国硬X射线调制望远镜的Crab脉冲星观测数据,研究了不同能段脉冲轮廓差异.其次,系统地研究了面向导航应用的X射线探测器测试及处理方法,并利用地面测试系统完成了一款自主研发的聚焦型X射线探测器测试工作.通过数据分析得到,聚焦型探测器本底噪声为3.63×10-5ph/(cm~2·s~(-1)),工作能区为0.2～22.7keV,时间分辨率为4.17μs,空间响应约为5′,能量非线性为0.52%,能量分辨率优于200eV@5.7keV,典型探测效率为39.18%@4.51keV.聚焦型X射线探测器在弱脉冲信号及强背景噪声下,均能还原出Crab脉冲星脉冲轮廓,在2 400s内能够探测到辐射流量弱于背景噪声10倍的脉冲信号.结果表明,该款聚焦型探测器性能优秀,能够满足导航脉冲星(如PSR B1509)的空间观测需求,也验证了测试方法的可行性.     

基于单片有源像素传感器的探测模块测试研究

硅像素探测器因具有优异的空间分辨率、极高的耐计数能力和较低的功耗等优点,近年来已被广泛应用于高能对撞机实验的顶点探测器和内径迹探测器.基于MIMOSA28芯片的硅像素探测器研究是北京谱仪Ⅲ漂移室内室的升级预研方案之一,该方案计划建造一个漂移室内室1/10规模的模型.探测模块是该模型的基本探测单元.为了对探测模块的性能进行研究,搭建了实验室测试系统.该系统主要由五层探测模块、读出电子学系统以及数据获取系统组成.本文围绕带有触发标记的连续数据读出方法的实现、探测模块的噪声水平和放射源响应测试以及击中位置重建算法研究展开.测试结果验证了探测模块工作性能良好,触发读出逻辑正确,而且重建算法准确有效,为后续探测模块性能的进一步研究奠定了基础.     

30.4nm极紫外成像探测器的实验研究

报导了最新研制的30.4 nm极紫外成像探测器的实验研究结果.该探测器采用了楔条形阳极(WSA)、高增益v型级联微通道板组件、低噪声电子读出系统等先进技术,利用单光子计数成像技术在实验审成功获得了模拟图像.搭建了相应的实验系统,对探测器成像的线性度、空间分辨率、暗计数等性能进行了实验研究.结果表明,该探测器具有φ45 nm的有效面积,空间分辨率优于100μm,暗计数率低[0.4 count/(cm2·s]、成像线性度好、结构简单等优点.     

一种聚焦型X射线探测器在轨性能标定方法

X射线探测器是X射线天文观测及脉冲星导航的核心器件,受发射振动、高能粒子辐射损伤及元器件老化等影响,X射线探测器空间观测性能会逐渐变化,X射线探测器在轨标定有利于观测天体X射线辐射信息的准确获取及精确建模.研究利用了脉冲星辐射能谱标定X射线探测器性能的方法,能较好地消除探测器本底及空间环境噪声的影响,通过处理脉冲星导航试验卫星(XPNAV-1卫星)的Crab脉冲星观测数据,评估了我国首款聚焦型X射线探测器的在轨性能.计算结果表明,XPNAV-1卫星上聚焦型X射线探测器的有效面积在0.6-1.9 keV能段内优于2 cm~2,其中在0.7 keV能量处取得最大值3.06 cm~2,探测效率约10%;有效面积随着探测能量增大而减小,在2—3.5 keV能段内有效面积约为1 cm~2,而大于5 keV能段的有效面积约为0.1 cm~2,且此能段估计精度明显受光子统计误差影响.同时研究了考虑能量响应矩阵的探测器有效面积标定新方法,利用地面性能测试中五个特征能谱处的能量分辨率重构其能量响应矩阵,重新标定了聚焦型X射线探测器有效面积,发现该能量响应矩阵对结果影响较小.最后建议观测某些超新星遗迹监测能量分辨率及能量线性等指标的变化.     

基于方差最小的高光谱目标探测算法研究

目标探测技术是遥感理论与应用中的重要领域之一,由于高光谱遥感图像能够同时提供地物目标的辐射、几何和光谱信息,与其他多光谱遥感图像相比,能更好地进行目标识别。从信息论中的自信息概念出发,针对探测结果影像中目标突出且信息确定性强的特征,提出了基于方差最小(BVM)的目标检测算子。利用不同空间分辨率和光谱分辨率的高光谱影像数据进行实验,并与约束能量最小化(CEM)算子的应用效果进行了比较分析。实验结果表明,基于方差最小的算子具有更稳健的探测性能。     

基于锥形硅纳米线色彩分辨探测能力仿真

基于拜尔滤波片(bayer filter)彩色成像技术在集成度和分辨率都已经接近极限,无滤波片(filter-free)的彩色成像单元得到广泛的关注和研究.纳米线自身腔模式可以实现对不同能量的光空间分布,通过对纳米线形貌调控实现色彩分辨探测.本文使用有限元法构建了能依靠自身结构完成分光目的,能够作为光探测器的锥形纳米线器件.数值模拟结果显示,能够根据器件的顶半径、底半径、长度和材料等相关参数调整器件涵盖的波长范围和分辨率等重要参数,并具体分析了如何进行调控.同时进一步分析了该结构在实际制备器件时以及不同角度入射光下的器件性能.这些研究结果对于将锥形结构纳米线作为光探测器的实际应用有重要的参考意义.     

全尺寸CMS RE1/2阻抗板探测器样器束流测试结果

介绍了CMS RE1/2 全尺寸阻抗板探测器的束流测试结果.探测器气体室的阻抗板表面采用不需要淋油的特殊光洁处理,外支撑框架采用铝质蜂窝板,以保证足够的强度以及整个RPC所占空间尽量小.在GIF的束流测试结果表明该样品在高辐射本底下能够达到满探测效率.时间分辨率以及噪声水平都符合CMS实验的要求.     

高纯锗探测器在近代物理实验教学科研中的应用

高纯锗(HPGe)探测器是上个世纪70年代发展起来主要用于探测?射线的实验仪器。因其具有能量分辨率高、线性范围宽、探测效率高、性能稳定等优点,被广泛应用于核辐射探测领域中。本文对HPGe的基本结构、探测原理、技术发展以及在大学近代物理实验教学科研中的应用进行了详细阐述。     

用于脉冲n/γ混合场γ强度测量的ICI探测器

研制成功一种基于康普顿效应, 用于脉冲裂变n/γ混合场γ强度绝对测量的新型辐射探测器—ICI(绝缘体－导体－绝缘体)探测器. 除具有现有真空康普顿和介质康普顿探测器时间响应快、线性电流大、抗辐射干扰能力强等优点外,该探测器从结构上抑制了真空康普顿在快脉冲γ测量中的前后负冲信号, 并且工作时不需要高真空, 而γ灵敏度却与同尺寸介质康普顿探测器相当. 由于其探测灵敏介质厚度小于2mm, 因而在群脉冲辐射探测中, 不会显著影响后续和周围探测器的 测量环境, 是一种探测脉冲γ射线较理想的探测器.     

Portable gamma spectrometry with cerium-doped lanthanum bromide scintillators: Suitability assessments for luminescence and electron spin resonance dating applications

Cerium-doped lanthanum bromide (LaBr₃:Ce) crystals offer a range of improved scintillation properties over traditional NaI:Tl crystals for in situ gamma spectrometry. At present, however, it remains unclear whether the internal radioactivity of LaBr₃:Ce detectors compromises their suitability for low-level activity radioisotope measurements of natural sedimentary deposits, such as those required in luminescence and electron spin resonance (ESR) dating. In this study we investigate the suitability of a commercial LaBr₃:Ce detector for measuring individual concentrations of ⁴⁰K, ²³⁸U and ²³²Th using predefined ‘energy windows’ from gamma ray spectra. Performance tests have been undertaken using reference materials with well-constrained radioisotope concentrations (the Oxford calibration blocks) and compared with results obtained for a NaI:Tl detector of the same geometry. These tests reveal that the LaBr₃:Ce detector has a non-negligible intrinsic activity that needs to be accurately quantified prior to measuring any gamma ray spectra in the field. Compared to the NaI:Tl detector, the energy resolution of the LaBr₃:Ce detector is improved by a factor of two, or more, for the main indicator isotope photopeaks in the ⁴⁰K, ²³⁸U and ²³²Th decay series. Signal-to-noise ratios for the LaBr₃:Ce detector show a 25-35% improvement over those of the NaI:Tl detector. In addition, the LaBr₃:Ce detector is characterised by suitable energy linearity over the full spectral range of interest for the ⁴⁰K, ²³⁸U and ²³²Th decay series. Replicate gamma ray measurements made with the LaBr₃:Ce and NaI:Tl detectors for 20 natural sedimentary samples from the Lower Tejo River basin, Portugal, and the Duero River basin, Spain, yield consistent radioisotope concentrations and gamma dose rate estimates. These results are encouraging and suggest that LaBr₃:Ce detectors can provide suitable estimates of individual radioisotope concentrations in low-level activity (0.5-1.5 Gy/ka) environments, providing that their intrinsic activity is adequately measured and subtracted from field spectra. Our comparison also reveals that subtraction of the intrinsic activity from LaBr₃:Ce spectra produces a significant reduction in the precision with which radionuclide concentrations can be determined using the ‘energy windows’ approach. This shortcoming necessitates longer counting times in natural sedimentary environments and overshadows the practical advantages that LaBr₃:Ce detectors might otherwise offer for luminescence and ESR dating applications.     

GdBr3:Ce in glass matrix as nuclear spectroscopy detector

An alumina-silica glass cylinder with cerium-activated gadolinium bromide, 2.5 cm in diameter and 3 cm long was cast to form a scintillation detector for spectral analysis of nuclear radiation, especially gamma rays. The detector, operated with a conventional photomultiplier tube and associated power supply, amplifier, and multichannel analyzer, shows for the first time for this material system a set of spectra that include well-defined full-energy gamma-ray peaks from 59.5 keV to 2500 keV. The full-energy peaks were characterized in terms of pulse height linearity, resolution, and counting efficiency. Energy spectral resolution also was demonstrated for alpha particles, beta particles, and ²³⁹Pu/Be neutrons. Gamma-ray detection efficiency was comparable to a conventional NaI(Tl) detector of similar volume but peak resolution at 662 keV in this new detector type was currently only 27%, compared to about 7% for the NaI(Tl) detector. Improved light output and thus resolution is being sought by optimizing glass compositions and processing.     

基于FPGA的数字反符合γ谱仪系统设计

本文设计了基于FPGA的数字反符合γ谱仪系统来降低天然本底和康普顿散射对低活度放射性测量的影响。该系统选用Φ145 mm×95 mm×80 mm的NaI （Tl）环形探测器与Φ75 mm×75 mm的NaI （Tl）主探测器构成反符合探测器,采用FPGA和高速ADC同步采样主探测器脉冲信号和反符合环形探测器输出信号。在FPGA中实现了核脉冲信号采集、缓存、反符合甄别、梯形成形等相关算法。在天然本底测量实验中,数字反符合γ谱仪系统的计数率为191.80 cps,本底抑制系数为2.69;对137Cs放射源的测量实验表明,在反符合探测器端面中心处,反符合测量峰总比为0.41,能量分辨率为6.99%;在反符合探测器侧面中间部位,反符合测量峰总比为0.30,能量分辨率为7.48%。实验结果表明,基于FPGA的数字反符合γ谱仪系统明显降低了天然环境本底和康普顿散射对测量的影响,适用于低活度放射性测量、现场就地放射性测量。     

Study of radiation background at the north crossing point of the BEPC in collision mode

Understanding the radiation background at the north crossing point (NCP) in the tunnel of BEPCII is crucial for the performance safety of the High Purity Germanium (HPGe) detector, and in turn of great significance for long-term stable running of the energy measurement system. Therefore, as the first step, a NaI(Tl) detector is constructed to continuously measure the radiation level of photons as background for future experiments. Furthermore, gamma and neutron dosimeters are utilized to explore the radiati...     

Using a LaBr3:Ce scintillator for positron annihilation lifetime spectroscopy

A LaBr₃:Ce scintillator has a high light output (~60000 p.e/MeV) and a short decay constant (<25 ns), which makes it good for time spectrometry. Compared with a BaF₂ scintillator, it can bear a much higher count rate, and can be coupled to photomultipliers without using a quartz window. In this work, a positron annihilation lifetime spectrometer (PALS) consisting of two bulks of φ25 mm×25 mm LaBr₃:Ce scintillator coupled to two XP20D0 photomultipliers, respectively, was built. A time resolution of FWHM=206 ps was measured for the PALS with a ⁶⁰Co source at the energy window for ²²Na. With this spectrometer, a reasonable lifetime value τ=221±4 ps in a pure Si sample is obtained, which means that the utilization of LaBr₃:Ce as the detector for a PALS is feasible.     

Use of CR-39 films for nuclear radiation shielding efficacy evaluation of lining materials for combat vehicles

All materials provide, to a lesser or greater extent, shielding against nuclear radiations. Armoured fighting vehicles (AFVs) have steel as the structural material, which appears to be a reasonably good gamma and neutron shield material but a shield of pure iron would not be equally effective against whole range of neutron energies as it has a few resonances in electron volt range, and it reduces energy of fast neutrons to lower energy neutrons. These neutrons will be absorbed through radiative capture and emit gamma radiations. Thus it is essential that an effective shield should contain a large amount of moderating material, hydrogen being preferred with low atomic number materials (B, C, Li) and lead (Pb) to ensure that the neutrons do not diffuse at intermediate energies in the shield as well as gamma attenuation will also take place. In order to have a suitable shield material for armoured vehicles which serves as neutron and gamma radiation attenuator, polyethylene polymer with fillers lining materials are preferred. These materials were evaluated against gamma and fast neutrons using radioactive sources for suitability to fitment into combat vehicle as per the requirement of protection factor values. The detector for gamma radiation was used as Nal(Tl) while for neutron, CR-39 film was used.      

爆炸物检测中典型样品的瞬发γ谱测量

在中子检测爆炸物的研究中,利用14 MeV中子与原子序数大于5的原子核相互作用可产生特征射线的特性,采用伴随粒子法结合D-T中子飞行时间技术,使用尺寸为12.5 cm20 cm的大体积NaI(Tl)探测器,对爆炸物所含元素C,N,O以及一些模拟炸药样品进行了瞬发谱测量。获得了几种典型样品的特征谱,并对其进行了分析。实验结果与欧盟同期结果进行了比较,表明本实验研究达到了目前国际同类实验的水平,可以为中子检测爆炸物识别技术提供实验支持。     

Evaluation of target photon dose mixed in mono-energetic neutron fields using 7Li(p,n)7Be reaction

Target photons mixed in the 144, 250 and 565 keV mono-energetic neutron calibration fields were measured using a cylindrical NaI(Tl) detector with 7.62 cm both in diameter and in length. The ambient dose equivalent H*(10) of the photons was evaluated by applying the “G(E) function” to the measured pulse height spectrum. Neutrons induce photons by nuclear reactions in the NaI(Tl) detector and affect the pulse height spectrum. In order to eliminate the influence of these neutron events, the time-of-flight technique was applied with operating the accelerator in the pulse mode. The ratios by the ambient dose equivalent H*(10) of the photons to the 144, 250 and 565 keV neutrons were evaluated to be 3.3%, 4.7% and 0.9%, respectively. Although high energy photons ranging from 6 to 7 MeV are emitted by the ¹⁹F(p,αγ)¹⁶O reactions, the dose of the target photons is low enough to calibrate neutron dosemeters except for ones with high sensitivity to the photons.     

Nuclear emissions during self-nucleated acoustic cavitation

A unique, new stand-alone acoustic inertial confinement nuclear fusion test device was successfully tested. Experiments using four different liquid types were conducted in which bubbles were self-nucleated without the use of external neutrons. Four independent detection systems were used (i.e., a neutron track plastic detector to provide unambiguous visible records for fast neutrons, a detector, a NE-113-type liquid scintillation detector, and a NaI gamma ray detector). Statistically significant nuclear emissions were observed for deuterated benzene and acetone mixtures but not for heavy water. The measured neutron energy was 相似文献   

Evolution of nuclear spectroscopy at Saha Institute of Nuclear Physics

Experimental studies of nuclear excitations have been an important subject from the earliest days when the institute was established. The construction of 4 MeV proton cyclotron was mainly aimed to achieve this goal. Early experiments in nuclear spectroscopy were done with radioactive nuclei with the help of beta and gamma ray spectrometers. Small NaI(Tl) detectors were used for gamma-gamma coincidence, angular correlation and life time measurements. The excited states nuclear magnetic moments were measured in perturbed gamma-gamma angular correlation experiments. A high transmission magnetic beta ray spectrometer was used to measure internal conversion coefficients and beta-gamma coincidence studies. A large number of significant contributions were made during 1950–59 using these facilities. Proton beam in the cyclotron was made available in the late 1950’s and together with 14 MeV neutrons obtained from a C-W generator a large number of short-lived nuclei were investigated during 1960’s and 1970’s. The introduction of high resolution Ge gamma detectors and the improved electronics helped to extend the spectroscopic work which include on-line (p ₇ p′γ) and (p ₇ nγ) reaction studies. Nuclear spectroscopic studies entered a new phase in the 1980’s with the availability of 40–80 MeV alpha beam from the variable energy cyclotron at VECC, Calcutta. A number of experimental groups were formed in the institute to study nuclear level schemes with (α ₇ xnγ) reactions. Initially only two unsuppressed Ge detectors were used for coincidence studies. Later in 1989 five Ge detectors with a large six segmented NaI(Tl) multiplicitysum detector system were successfully used to select various channels in (α ₇ xnγ) reactions. From 1990 to date a variety of medium energy heavy ions were made available from the BARC-TIFR Pelletron and the Nuclear Science Centre Pelletron. The state of the art gamma detector arrays in these centres enabled the Saha Institute groups to undertake more sophisticated experiments. Front line nuclear spectroscopy works are now being done and new informations are obtained for a large number of nuclei over a wide mass range. Currently Saha Institute is building a multi-element gamma heavy ion neutron array detector (MEGHNAD), which will have six high efficiency clover Ge detector together with charged particle ball and other accessories. The system is expected to be usable in 2002 and will be used in experiments using high energy heavy ions from VECC.