NaI(Tl)晶体探测器对面源的γ绝对探测效率

用数值积分方法计算了ＮａＩ（Ｔｌ）晶体探测器对Ｍａｒｉｎｅｌｌｉ Ｂｒｅａｋｅｒ型容器内表面源的γ绝对探测效率。     

NaI(Tl)探测器的源几何特性对峰总比影响模拟研究

利用蒙特卡罗工具Geant4模拟了~(137)Cs和~(60)Co这两种放射源的几何形状以及探测距离这两个因素对γ射线在NaI(Tl)闪烁体探测器内能量沉积的影响。研究结果表明,当放射源的几何形状不一样时,不同的核素在峰总比达到最大时的探测距离不一样,模拟结果为放射性测量提供了参考。     

基于三NaI(Tl)晶体探测器的放射源定位研究

设计了一种三NaI(Tl)晶体组成的γ射线源定位探测器系统,并通过模拟仿真及实验研究了三NaI(Tl)晶体探测器在137Cs辐射场中全能峰占比计数随距离及入射粒子方向变化的关系。结果表明:在远距离探测情况下,采用全能峰占比法可以有效消除源与探测器间距对角度分辨的影响。对于探测距离约为2.58 m的1.36×106Bq的137Cs源,测量的最大角度偏差≤1.72°,定位位置相对偏差为3.71%。     

Monte Carlo方法对不同尺寸NaI（Tl）晶体探测效率的刻度

应用蒙特卡罗方法,在VC++开发平台下编制了可以自定义NaI晶体尺寸的软件,实现对不同能量的γ射线的探测效率的计算.根据计算得到的数据矩阵拟合出不同体积探测器对点源的效率函数,并确定出函数的参数.     

基于点源~(133)Ba刻度~(131)I探测效率的面积加权法

介绍了利用~(133)Ba点源的γ能峰(与~(131)I的γ能量相近)通过面积加权法对NaI(Tl)探测器模拟刻度碘盒中的~(131)I探测效率的原理和方法.其模拟刻度结果与标准刻度方法效率(~(133)Ba和~(131)I碘盒标准源刻度探测效率)进行了比较,其相对误差分别为7.15%和1.34%.研究表明,~(133)Ba点源面积加权法刻度NaI(Tl)探测器对碘盒中的~(131)I探测效率是一种简便而可靠的方法.     

应用前处理和NaI(Tl)探测器对稀土元素进行中子活化法测定

中子活化法分析矿石、土壤中稀土元素,用带NaI(Tl)探测器的多道γ谱仪测定时,因其分辨率低,元素之间干扰严重,解谱是比较困难的。但由于NaI(Tl)探测器效率比较高,且目前国内不少多道γ谱仪配备这种探测器。如能找出一种快速有效的分离和富集稀土的方法,对矿石和土壤样品进行前处理,以消除其他元素对稀土元素的干扰,同时再采用较好的解谱方法,尽可能降低稀土元素之间干扰带来的误差的话,利用NaI(Tl)多道γ谱仪分析矿石、土壤中稀土元素,也是一种可取的方法。我们用PMBP柱萃淋法     

大体积NaI(Tl)探测器性能研究

利用蒙特卡洛方法,对不同体积NaI(Tl)探测器的探测效率进行了计算.对圣戈班(Saint-Gobain)5"×8"NaI(Tl)探测器的能量分辨及时间响应进行了测试.在14 MeV氘-氚中子源照射条件下,测量模拟样(化学式:HCNO)的特征瞬发伽马谱,与国产φ"×4"NaI(Tl)探测器进行了比较.结果表明,圣戈班的...     

车载式NaI(Tl)大晶体组的多道谱仪

文章介绍车载式NaI(Tl)大晶体组的γ多道谱仪,该谱仪选用2个10 cm×10 cm× 40 cm NaI(Tl)方晶体探头,采用高速ADC集成芯片、USB微控制器等先进技术,具有实时、灵敏度高、识别核素的特点,可用于搜寻失控放射性源、核与辐射突发事件中的快速探察和应急监测、环境辐射调查等工作.     

井型HPGe探测器探测效率的MC模拟

采用MC方法对井型HPGe探测器全能峰探测效率进行虚拟刻度。通过改变点源在井中的位置,研究了其探测效率变化规律,并进行了实验验证;同时模拟计算了探测器对0.1~1Me V能量的探测效率。模拟与实验结果表明:137Cs放射源在井中不同位置的实验测量结果与模拟值最大相对误差6.8%,最小相对误差1.5%;探测效率随放射源离井底距离增加而减小,随入射射线能量增大而减小。     

应用蒙特卡罗方法确定NaI探测器的点源效率函数及其参数

为了探讨NaIγ探测器对点状γ射线源(以下简称"点源")的探测效率与点源空间位置之间的关系,采用蒙特卡罗方法通用程序模拟计算了NaIγ探测器对空间不同位置处137Cs、60Co点源的探测效率.根据模拟计算结果,通过数值拟合方法,确定了NaI探测器对点源的探测效率函数及其参数.研究表明,应用蒙特卡罗模拟方法确定NaIγ探测器对于点源的探测效率函数及其参数是一种简便、有效的方法.     

大体积阱式NaI(Tl)探测器的效率计算与测量

使用蒙特卡罗方法模拟计算了一个用于4πγ计数的大体积阱式NaI(Tl)探测器的效率和能谱。采用一系列单能γ源标定探测器,对计算结果进行检验,其结果基本一致,两者间的最大偏差不超过±8%,证明计算结果是可靠的。     

NaI(Tl) 闪烁谱仪峰总比的蒙特卡罗计算

简单分析NaI(Tl）闪烁谱仪探测原理的基础上，运用蒙特卡罗程序MCNP计算了该谱仪对不同能量点源的峰总比（或光分数），并同实验结果做了对比，解释了计算结果比实验值偏高的原因。     

用井型 Nal(TI)探测器绝对测量~(125)I活度

本文叙述了用井型 NaI(T1)探测器的符合脉冲高度分布绝对测量~(125)I 活度的方法。用目前比较精确的核参数推导了计算公式。初步研究了样品体积和样品瓶的几何条件对测量结果的影响。测量结果的合成不确定度小于1%.     

Monte Carlo simulation of the NaI(Tl) detector response to measure gold activated foils

This work deals with the implementation of a NaI(Tl) detector for the assessment of the specific saturation activities of pure gold foils after neutron irradiation. These gold foils can be placed in the centre of a set of polyethylene spheres with different diameters. This configuration, known as a passive Bonner sphere system, is suitable to measure neutron spectra normally extended over a wide energy range containing up to 11 decades (from thermal to a few MeV), at places where the neutron field is very intense, high frequency pulsed or where it is mixed with an important high-energy photon component. The MCNPX code was used to evaluate the NaI(Tl) responses to different incident photon energies in terms of pulse-height distributions. An experimental validation of the calculated NaI(Tl) responses, using certified standard sources at a given measurement arrangement, indicates that MCNPX is a valid tool for routine calibration and benchmarking studies of this detector. A good agreement is found between the measured pulse-height distributions of the certified standard sources and those obtained from MCNPX simulations. As a preliminary application, a bare disc Au foil was directly exposed to a Bremsstrahlung photon beam at the isocentre of an 18 MV medical LINAC, in order to test the suitability of this activation material to measure the photo-neutrons generated in such facility. Two differentiated main photo-peaks, arising from ¹⁹⁶Au and ¹⁹⁸Au predominant γ-ray emissions, were observed. The two isotopes are produced mainly by the photonuclear, ¹⁹⁷Au(γ, n)¹⁹⁶Au, and radiative capture, ¹⁹⁷Au(n, γ)¹⁹⁸Au, reactions of, respectively, high-energy photons and thermal neutrons on the gold foil. From the measured ¹⁹⁸Au saturation activity, a rough estimation of (378 ± 68) × 10⁴ cm⁻² Gy⁻¹ was derived for the thermal neutron flux within the LINAC treatment room. This value, although being very approximate, is comparable to those reported by other authors for similar LINAC facilities but with different treatment room configurations, nominal acceleration potentials and Bremsstrahlung photon irradiation areas.     

基于傅里叶变换的NaI(Tl)仪器谱散射本底估计方法

有效地估计NaI(Tl)仪器谱的散射本底可提高仪器的分析精度。本文提出了一种基于傅里叶变换的散射本底估计方法。通过在模拟谱线和实测NaI(Tl)仪器谱上的应用,表明该方法适用于NaI(Tl)仪器谱数据处理,能自主、有效估计散射本底。     

Extraction of full energy peak of 137Cs from in situ NaI (Tl)gamma-ray spectrum

A Levenberg–Marquardt Gaussian fitting algorithm has been used for analyzing the overlap of three peaks(the 583-ke V peak of~(208)Tl, the 609-ke V peak of214 Bi, and the 662-ke V peak of~(137)Cs) using an in situ Na I(Tl) scintillation spectrometer. The algorithm, in addition,was compared with a genetic algorithm used for multiple deconvolution. The three fitted peak areas(583, 609, and662 ke V) were calculated from the measured gamma-ray spectra obtained from a simulation experiment in which a~(137) Cs source was buried at different soil depths(from 18 to38 cm). The application of the Levenberg–Marquardt algorithm yielded similar results compared to the genetic algorithm. A lack-of-fit test showed that the fitting is good when the instrumental noise levels were estimated from replicated analyses. The relative fitting error of the total net area and the residual standard deviation were within 5 %and 0.04, respectively, and the goodness of the fitting was better than 0.98. While the methods used in this paper give high performance, the results may lead to incorrect estimation when the signal-to-noise ratio is smaller than-30 d B. This study is useful for the determination of radioactive specific activity of~(137) Cs by in situ spectrometry.     

An inversion decomposition method for better energy resolution of NaI(Tl) scintillation detectors based on a Gaussian response matrix

NaI(T1) scintillation detectors have been widely applied for gamma-ray spectrum measurements owing to advantages such as high detection efficiency and low price.However,the mitigation of the limited energy resolution of these detectors,which detracts from an accurate analysis of the instrument spectra obtained,remains a crucial need.Based on the physical properties and spectrum formation processes of NaI(T1) scintillation detectors,the detector response to gamma photons with different energies is represented by photopeaks that are approximately Gaussian in shape with unique full-width-at-half-maximum(FWHM) values.The FWHM is established as a detector parameter based on resolution calibrations and is used in the construction of a general Gaussian response matrix,which is employed for the inverse decomposition of gamma spectra obtained from the detector.The Gold and Boosted Gold iterative algorithms are employed to accelerate the decomposition of the measured spectrum.Tests of the inverse decomposition method on multiple simulated overlapping peaks and on experimentally obtained U and Th radionuclide series spectra verify the practicability of the method,particularly in the low-energy region of the spectrum,providing for the accurate qualitative and quantitative analysis of radionuclides.     

车载NaI(Tl)系统搜索~(241)Am点源的测量参数优选

通过分析车载Na I(Tl)系统的信噪比与车载241Am点源效率分布特征,实现了车载Na I(Tl)系统搜索241Am点源的测量参数优选。结论表明:车载Na I(Tl)系统测量信噪比最大时对应的获谱时长与行驶速度呈反比,最优的扫描间距为160 cm。在最优测量条件下,车载Na I(Tl)系统单次测量的面积等于测量步长乘以扫描间距,应小于Na I(Tl)探测器对γ放射源的主要效率覆盖面积。     

NaI(Tl)γ谱的计算机稳峰技术

介绍了一种改进型NaI(Tl)γ谱仪的稳谱技术。该稳谱技术基于241Am源的等效γ峰作为系统的参考峰,根据参考峰位偏差运用数字PID调整可编程增益放大器来稳谱,是一种“硬件 参考源 软件”的稳谱技术。这种计算机稳谱技术具有稳定度高,稳谱速度快等优点。     

Maximum scintillation yields in NaI(Tl) and CsI(Tl) crystals estimated from the scintillation model for liquid rare gases

The maximum scintillation yields in NaI(Tl) and CsI(Tl) crystals were estimated theoretically by applying the scintillation model for liquid rare gases to crystal scintillators. Average energies required to produce one scintillation photon in the maximum scintillation yield, W_so, were estimated to be 10.6 ± 0.3 or 11.6 ± 0.3 eV for NaI(Tl) and 11.6 ± 0.3 or 12.5 ± 0.3 eV for CsI(Tl). The new experiment on scintillation yields gives W_so of 10.8 ± 2.0 eV for NaI(Tl) and 11.3 ± 2.1 or 9.3 ± 1.7 eV for CsI(Tl). The values show good agreement with the theoretical estimations. These results demonstrate that the scintillation model in liquid rare gases is applicable to inorganic scintillators such as NaI(Tl) and CsI(Tl) crystals.