LaBr_3:Ce(5%)闪烁探测器的MC研究

近年来一种采用LaBr3:Ce晶体的闪烁探测器被研发出来,这种新型探测器比NaI(Tl)探测器具有更高的能量分辨率,在662 keV大约为3%。利用蒙特卡罗通用程序MCNP4C分别模拟计算了LaBr3:Ce晶体和NaI(Tl)晶体的γ能谱,模拟能谱与相应的实验测量能谱符合很好。研究还发现晶体尺寸大小对能量分辨率没有影响,能量分辨率不随晶体体积的增加而提高。同样晶体尺寸下通过模拟探测不同入射能量γ射线的峰总比R(E)计算值与NaI(Tl)晶体的模拟值和实验值比较发现,LaBr3:Ce晶体对中高能量γ射线的探测效率较高,而在较低能量时探测效率低于NaI(Tl)晶体。     

环境水样自动监测装置的效率标定及Monte Carlo模拟

为获得自动取样监测装置中的NaI(Tl)探测器对于低水平环境水样中人工放射性核素137Cs比活度,对NaI(Tl)探测器γ能谱响应进行了实验标定与Monte Carlo模拟,分别模拟了探测器对137Cs点源的能谱响应,探测器置于铅室内137Cs溶液中央的能谱响应。探测效率与峰总比的模拟计算结果与实际值基本一致。结果表明,利用经较高比活度实验结果验证的MC计算模型,可校正低活度水平环境水样的测量值,为在线监测方法的建立提供了技术支持。     

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...     

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.     

野外γ谱仪刻度的蒙特卡罗模拟

用蒙特卡罗方法对NaI(Tl)野外γ谱仪刻度进行模拟,计算谱仪的响应系数.通过与实验的比较,研究利用蒙特卡罗方法对NaI(Tl)野外γ谱仪进行刻度的可行性.结果表明,当模拟探测器对137Cs的能量分辨率从8%～14%变化时,模拟结果与实验结果的差别在12%以内.     

MCNP能峰展宽的NaI探测效率研究

本文利用光子和电子耦合输运MC程序的电子脉冲计数类型的能峰展宽模拟计算了NaI(T1)探测器的γ能谱,与实验测量的能谱符合较好.然后利用MCNP计算了NaI(T1)对不同能量γ射线的探测效率(峰总比),结果与实验值一致,验证了这种计算方法用于模拟NaI(T1)对γ能谱的探测效率是可行的.     

海洋γ谱连续监测方法模拟

通过蒙特卡罗程序MCNP(Monte Carlo N Particle Transport Code)建立了海洋γ谱连续监测的测量模型,模拟计算不同能量γ射线在海水中的衰减情况和有效探测距离。根据我国近岸海域海水中天然放射性核素活性浓度,模拟得到不同晶体尺寸NaI探测器连续监测的本底谱,分析能量分辨率对全能峰本底计数率的影响并探讨了影响NaI探测器能量分辨率的因素。最后针对我国核电厂周围海域中重点关注的人工放射性核素,并假设不同尺寸NaI晶体在能量662 keV处分辨率保持7.0%不变的条件下,分别计算了不同尺寸NaI晶体探测器在海洋γ谱连续监测中的探测效率、本底计数率和最小可探测活性浓度等技术参数。模拟结果为海洋或其它水体中γ谱连续监测方法的应用提供技术参考。     

蒙特卡罗方法模拟放射源位置对井型NaI(Tl)晶体探测效率的影响

利用Geant4数值计算程序,对放射源137Cs和60Co发射的单能γ射线(0.662 MeV和1.331MeV)经过井型NaI(Tl)晶体探测器后的能谱进行了蒙特卡罗模拟,并通过改变放射源在井型NaI(Tl)晶体中的位置对探测效率的影响做了进一步的研究。计算结果表明:对比常用的圆柱形NaI(Tl)闪烁探测器,由于井型NaI(Tl)晶体对放射源所张立体角很大,所以其对γ射线的源峰探测效率更高,并随着放射源在井内高度的增加而逐渐减小;在固定了放射源在晶体井下深度的情况下,放射源位置在水平面内的变化对源峰探测效率的影响并不大。     

海水就地测量探测器探测效率的Monte Carlo研究

为研制用于海洋放射性监测(特别是核电海域)的海水中就地γ能谱仪,利用Monte Carlo程序MCNP,采用分层抽样、结果加权叠加的方法,模拟了海水中NaI(Tl)、HPGe、CdZnTe、LaBr等探测器在理想状况下对几种有关γ射线的能谱,并分析计算出以上各探测器对海水中137Cs6、0Co5、4Mn4、0K等放射性核素的探测效率、有效探测距离。结果表明,各探测器对γ放射性核素的有效探测距离约为20~40cm,具体数值与探测器种类和γ射线能量有关。综合探测效率和能量分辨率而言,LaBr探测器具有最好的实际应用价值。该结果为实际的海水中就地γ能谱仪的探测器选择和应用提供了重要参考。     

Simulation of the Carrier Trapping Effect in a Schottky CdTe Detector by Considering a Nonuniform Electric Field

In order to simulate the low-energy tail in the response function of a Schottky CdTe detector, which is a high-resolution room temperature X- or γ-ray spectrometer, we introduced the effect of a nonuniform electric field within the detector to the response function by a Monte Carlo calculation using the EGS5 code. The simulated response functions were compared with measurements for γ-rays from ¹⁰⁹Cd, ²⁴¹Am, ¹³³Ba, and ⁵⁷Co sources. The present method successfully reproduced the low-energy tail due to the charge carrier trapping effect, while the conventional model assuming a uniform electric field underestimated the low-energy tail significantly, particularly for higher energy γ-rays.     

Transmission of Gamma-Rays from 60Co Monodirectional Source through Slabs of Polyethylene and Iron

Scattered γ-rays were measured with 5-in. diameter by 5-in. long Nal(Tl) scintillator for the purpose of obtaining information on the transmission of ⁶⁰Co γ-rays incident to polyethylene and iron slabs, and layered combinations thereof. The primary γ-rays were collimated, and the detector was used without collimator. The spectra of scattered γ-rays above 300 keV were quite similar to each other irrespective of material and thickness when the scattering angle and scatterer thickness in mean free path units were normalized.     

YAP：Ce闪烁探测器γ射线能量响应研究

使用新型YAP：Ce无机晶体配大线性电流光电倍增管组成闪烁探测系统，采用散射法将⁶⁰Co源（约2.2×10¹⁴ Bq）散射为单能γ射线，实验测量探测器系统的γ射线灵敏度，并结合计算机数值模拟计算对数据进行分析处理。新型YAP：Ce无机晶体对γ射线的灵敏度相对较高，是同体积CeF₃晶体的10倍多。采用YAP：Ce无机晶体比CeF₃晶体更有利于γ射线测量。      

Environmental Gamma-Ray Exposure Rates Measured by In-Situ Ge(Li) Spectrometer

A conversion function (G(E) function) was determined to obtain an exposure rate directly from a γ-rays spectrum measured by an in-situ Ge(Li) spectrometer. In order to verify the utility of the G(E) function method, three kinds of detector, namely, a portable Ge(Li) detector, a Nal(Tl) detector and an ionization chamber, were used to measure exposure rate due to environmental γ-rays at the same place, and the measured values of exposure rate were compared with each other. Two exposure rate values were obtained from a γ-ray spectrum measured by the Ge(Li) detector, using two different methods, namely, the G(E) function method and the HASL method. The average of exposure rates obtained by four different methods was 4.15 üR/h, and the deviation was 15% of the average.

By applying both the G(E) function method and the HASL method to an environmental γ-ray spectrum, a total exposure rate can be determined directly without information on the distribution of the radionuclides in soil, and individual exposure rates due to ⁴⁰K, ²³⁸U and ²³²Th series and ¹³⁷Cs of the known distribution in soil can be also determined.     

Gamma-Ray Spectrometric Determination of Isotopic Ratios of Plutonium

Abstract

Plutonium samples (3–30 μg) of various isotopic compositions were measured with a high-resolution Ge(Li) detector. The γ-rays counted are the 43.5 keV of ²³⁸Pu, the 38.7, 51.6 and 129.3 keV of ²³⁹Pu, the 45.2 keV of ²⁴⁰Pu, and the 148.6 keV of ²⁴¹Pu. To estimate the relative photopeak efficiencies of the γ-rays, an empirical curve was derived from measurements of the three γ-rays of ²³⁹Pu adopted as internal standard. Data treatment is described in detail as well as the method of correction to account for the activities of ²³⁷U and ²⁴¹Am inherently accumulating in the plutonium sample. The branching ratios of the γ-rays of plutonium were also evaluated by comparing the γ-ray spectrometric results with mass-spectrometric data.     

γ射线探测器能量响应标定技术

叙述了γ射线探测器能量响应的标定原理和方法，即利用Compton散射将强⁶⁰Co源的1.25MeVγ射线转换为0.36~1.02MeV(25°~90°)范围内任意能量的系列单能γ射线；采用辐射屏蔽技术和提高能量分辨率方法对γ射线探测器进行了该能区的能量响应标定；通过MCNP程序对探测器的能量沉积趋势和不同散射角散射γ射线的能量分布进行模拟计算。结果表明：该标定系统信噪比达到了20∶1左右，能量分辨率约为6%，0.66MeV的灵敏度与标准¹³⁷Cs源直照标定的灵敏度基本一致。     

NaI(TI)探测器晶体体积对主要性能影响研究

使用~(137)Cs、~(60)Co和~(22)Na三种点射线源,分别探讨了由不同体积闪烁晶体组成的探测器对不同能量γ射线的峰效率、能谱响应及有效中心的影响。实验结果表明:随着闪烁晶体体积的不同,不同能量γ能谱光电峰的峰位及其能量分辨率都发生了变化。还发现探测器有效中心点的位置依赖于闪烁晶体的体积,其峰效率的倒数与探测器有效距离平方成反比。此实验结果可为改善不同体积NaI(Tl)闪烁探测器的能谱响应和高精度测量提供参考。     

脉冲中子全能谱测井闪烁探测器响应特性的蒙特卡罗模拟

利用蒙特卡罗方法模拟研究NaI和BGO晶体探测器对不同γ射线的响应。模拟结果表明,BGO晶体的光电峰和第一逃逸峰对计数贡献大,而NaI晶体的逃逸峰贡献大。对于井眼和地层流体分别为油和水砂岩地层,模拟改变NaI和BGO晶体探测器的直径和长度时的非弹性散射γ射线响应能谱,采用不同能窗处理方法对地层流体的分辨能力不同,选取光电峰和第一、第二逃逸峰对应的能量窗时,BGO晶体探测器比NaI晶体探测器测量的C/O（C与O的元素含量比）差值大,但受尺寸的影响不大;采用光电峰对应的能量窗时,BGO晶体探测器测量的C/O差值比NaI的大得多,且随尺寸的增加差值增大;能量道的漂移对C/O值影响较大,而能量分辨率对差值影响相对较小。     

叠层式探测器响应函数的理论计算和实验验证

光子能谱是脉冲辐射场中的重要参数.叠层式组合探测器可用于测量脉冲辐射场光子注量谱,而组合探测器对各种不同能量的光子的响应函数是光子能谱解谱的基础.本文用MCNP/4C对其响应函数进行了模拟计算,并采用热释光探测技术对典型能量点的γ射线的响应函数进行了实验验证.结果表明,叠层式组合探测器响应函数的理论模拟值和实验测量结果在实验测定精度内符合良好.     

Sensitivity of a new-developed neutron detector

We develop a kind of neutron detector, which consists of a polyethylene thin film and two PIN semiconductors connected face-to-face. The detector is insensitive to γ-rays. Its sensitivity to neutron has been calculated with MCNP program and calibrated by experiments, and the results indicate that the neutron sensitivity of the compensation detector will vary with polyethylene convel‘ter. The compensation PIN detector can be employed to measure pulse neutron in neutron and gamma mixture radiation field.