HPGe探测器效率模拟及符合相加校正技术研究

为提高高纯锗(HPGe)探测器测量低水平放射性核素活度的探测灵敏度,通常将样品置于距探测器较近的位置以提高探测效率,但近距离测量不可避免地会带来较严重的符合相加效应,影响活度测量的准确度。本文利用Geant4对HPGe探测器进行了峰效率模拟,并与混合标准刻度源的实验结果对比,表征了探测器内部几何结构;基于表征的探测器几何结构对探测器总效率进行了模拟,进而从物理机制上计算得到了符合相加效应校正因子,并将其用于全面禁止核试验条约(Comprehensive Nuclear Test Ban Treaty,CTBT)筹委会临时技术秘书处(Provisional Technical Secretariat,PTS)组织的2021年度放射性核素滤材样品能力验证,符合相加校正后的核素活度与参考值相对偏差小于3%,验证了计算的符合相加校正因子的准确性,解决了实验测量总效率刻度点受限、实验成本高等问题,为准确测量样品中的核素活度奠定了基础。

Methods for obtaining characteristic γ-ray net peak count from interlaced overlap peak in HPGe γ-ray spectrometer system

For a characteristic c-ray with interlaced overlap peak, and the case where its reliable and credible net count cannot be obtained using the current high-purity germanium(HPGe) multichannel γ-ray spectrum software, two new methods are proposed herein to obtain the γ-ray net peak count from the interlaced overlap peak in the HPGe cray spectrometer system, of which one is the symmetric conversion method based on Gaussian distribution and the other is where the energy average value of two close γ-rays is regarded as the γ-ray energy. The experimental results indicate that the two methods mentioned above are reliable and credible. This study is significant for the development of better γ-ray spectrum processing software for measuring complex γ-ray spectra concerning the nuclear reaction cross section, neutron activation analysis, and analysis of transuranium elements, using an HPGe detector.

Ballistic deficit compensation method for a large-volume HPGe detector at high count rates

A large-volume HPGe detector normally has a severe ballistic deficit due to its long rise time of the output signals.Despite the trapezoidal shaping algorithm adopted as a remedy to deal with the signals,the algorithm cannot fully eliminate the ballistic deficit in the case of a high counting rate.To resolve the problem,we propose a ballistic deficit compensation method that is based on the measurement of rise time of the signals before shaping.We find that the ballistic deficit after trapezoidal shaping has little relation to the time constant,but shows a quadratic relationship with the rise time and has a negative correlation with the shaping time.In the case of high count rates,the high resolution is handled by fitting the curve to the rise time and the amplitude deficit of the signal after shaping and by compensating for the signal amplitude after trapezoidal shaping.Tests indicate that when the count rate is about 100 kcps,the resolution of Co-60 improves from traditional 2.32 up to 1.91 keV,thus reaching a higher level.

Assessment of Radiological Contamination of Soils Due to Shipbreaking Using HPGe Digital Gamma-Ray Spectrometry System

A systematic study of the distribution of the Naturally Occurring Radioactive Materials as well as the anthropogenic radionuclide in the working environment of the Shipbreaking yards of Sitakunda, Chittagong, Bangladesh, has been carried out with an objective of establishing reliable base line data on the radiation level and hence to measure the radiation dose expose to the workers and to the inhabitants of the studied area. Fifteen Soil samples have been col-lected from five different Shipbreaking yards. Three sampling spots in each yard have been selected for having repre-sentative samples for the assessment of radioactivity releasing from 226Ra (238U), 232Th and their daughters and 40K us-ing the Digital Gamma-ray Spectrometry system coupled with a High Purity Germanium (HPGe;Canberra, 40% rela-tive efficiency, 1.8 keV resolution at 1332 keV of 60Co) detector and PC based Multichannel Analyzer (MCA, upto 16k channel). The software Genie 2000 (Canberra) and Hypermet PC have been used for data acquisition and gamma peak analysis, respectively. Each of fifteen soils (~200g) and two standards (IAEA-Soil-6 and 800Bq liquid 226Ra sprayed in Al2O3) were counted in cylindrical plastic pot using gamma spectrometry system for 20000 sec for the determination of activity concentrations of the radionuclides. The samples and standards were kept in air tied condition at least for 4 weeks before gamma counting to attain the radioactive equilibrium between daughters and parents of 226Ra (238U) and 232Th decay series. The Al2O3 based 226Ra standard was used for the construction of efficiency curve covering the wide gamma energy range. The IAEA-Soil-6 was used for quality control (QC) of the analysis. The homogeneity test and density corrections of Al2O3 based 226Ra standard were performed and implemented for the analysis. The results of ac-tivity concentrations have been used to assess the radium equivalent activities (Raeq) and the representative level index (Iγr) values in the experimental soil samples. The results have been compared with other global radioactivity measure-ments and evaluations.

HPGe and Scintillation Detectors Comparisons on Waste Drums Radioactivity Measurement

Two measurement systems, one being comprised of three HPGe detectors and the other being a 4π measurement system of the assembly of 10 sets of scintillation detectors, were compared for their measurement performance in operations of radioactive waste drum radioactivity measurement and clearance and release operation of decommissioning. The system features of the former were high costs, capable of identifying radionuclides, a measurement time of about 1000 sec. The system features of the latter were high sensibility, capable of identifying hotspots, a measurement time of about 100 sec. Various comparisons were made for the differences of the two systems on reference drums, whole-drum homogeneous and non-homogeneous metal drums and non-metal drums, whole-drums of different filling rates. The aim was to compare the differences of the two measurement systems in measuring radioactivity of critical radionuclides of 137Cs, 54Mn and 60Co.

Study of Annealing the Damaged HPGe Detector

High purity germanium detectors have important applications in many fields. Detector’s performance deteriorated significantly due to radiation of neutron. The annealing of damaged HPGe detector is expounded in this monograph. The experiment results indicate that raising the temperature to 70°C for five days, the restoration efficiency can reach 90%.

BNCT治疗束γ能谱仪的校准方法研究

受硼中子俘获疗法(BNCT)治疗束的特点所限,源项γ射线能谱的测量难度较大,国际上开展的相关工作很少,且未对其谱仪进行校准。为得到准确的源项γ能谱,本文主要开展了适用于BNCT治疗束γ能谱仪的校准方法研究。谱仪由高纯锗(HPGe)探测器及屏蔽系统组成,因为屏蔽效果很好,无法通过实验方法校准整个谱仪系统的γ响应。由于其主要影响因素是HPGe探测器的死层分布,谱仪可通过下述方法进行校准:对裸探测器进行校准,获取探测器的准确模型;利用精细测量及材料分析得到屏蔽体的精确模型,建立谱仪的计算模型;通过MCNP计算获得谱仪的响应函数。由此将结果溯源至相应的国家或国防标准,确保谱仪关键参数的准确可靠,为后续解谱工作奠定基础。

蒙特卡罗模拟确定HPGe探测器点源效率函数及参数

在探测器晶体体积一定的情况下,HPGe探测器点源效率主要由γ射线能量、角度和探测距决定。利用极坐标对点源进行空间定位,试验测试了不同角度和探测距条件下137Cs和60Co点源的γ能谱,同时采用MCNP程序模拟计算HPGe探测器不同角度与探测距条件下γ点源效率,并与实验值进行对比和校正。结果表明,探测角度在0-9π/24,γ点源效率模拟值与实验值之间全能峰净计数的相对偏差均在8%以内。最后对γ点源效率模拟值进行多元非线性回归,确定了在特征γ射线能量下,以角度和探测距为因变量的点源效率函数及其参数。

HPGe探测器点源效率与其空间位置的函数关系

本文采用蒙特卡罗(MCNP)模拟与实验相结合的方法,计算了HPGe探测器(美国Ortec公司产品,相对效率40%,对1332keV的分辨率为1.8keV)对空间不同位置、不同能量点源的探测效率,对Masayasu等[1]提出的点源径向表达式作了修正,改进了与实验值(或MC模拟值)的一致性;给出了HPGe探测器效率随点源位置变化的解析表达式;证明了应用MCNP模拟方法确定探测器对于点源的探测效率函数的可靠性和实用性,也有助于对体源效率的测量和计算。

基于蒙特卡罗的HPGe伽马谱仪无源效率刻度方法

采用MCNP5模拟与数学计算相结合,并利用探测器晶体几何的轴对称性,建立一种HPGe探测器的无源效率刻度方法。基于此方法的计算程序在使用过程中完全脱离MCNP5,运算时间为1～60s,可实现点源和同轴圆柱体源的效率刻度,能量范围为50keV～3MeV。程序计算结果与实验数据以及MCNP5直接模拟结果比较,误差分别不超过12%和7%,证明方法可行。

用于HPGe探测器效率标定的模拟气体刻度源的研制

准确校准测量系统的探测效率是HPGe探测器γ能谱法测量放射性气体活度的关键,放射性气体的半衰期一般较短且样品制备过程复杂,这些客观因素给效率校准工作带来很多不便。本工作提出了模拟气体刻度源的制备方案并进行了实验研究,所制备的模拟刻度源最小基质密度为0.043g/cm3,自吸收的影响小于0.5%。通过与效率参考值的比较表明,模拟气体刻度源的制备方案简单可行,所制备的模拟气体刻度源可代替气体标准源实现气体活度测量中HPGe探测器的效率校准以及探测效率的日常监督。

基于虚拟点探测器模型的HPGe探测器体源效率刻度

基于虚拟点探测器(VPD)模型应用平方反比定律,介绍了一种通过点源模拟实验进行HPGe探测器对圆柱体源样品的峰效率刻度方法。实验验证表明:在一定范围内利用该方法对圆柱体源进行效率刻度是合理可行的,并能获得较好的刻度结果,该方法可操作性强,可应用于工程实践。

应用蒙特卡罗方法表征HPGe探测器

采用蒙特卡罗方法计算HPGe探测器对光子的探测效率,需对计算模型参数进行确定。使用蒙特卡罗模拟计算和实验测量相结合的方法,对晶体死层厚度及冷指尺寸进行了表征。结果表明,使用此方法确定晶体参数模拟光子的探测效率,在59.54～1 408.1keV光子能量范围内,计算效率与实测效率相对偏差在5%以内,并进行了实验验证。

HPGe探测器能量刻度及探测效率模拟

X光机绝对光子数的测量在X射线计量中有着十分重要的意义,对其进行测量时需先将探测器的能量—道址函数进行刻度。本文使用放射源对HPGe探测器进行能量刻度,得到其能量—道址函数且其线性相关系数R2=0.999 84。论文结合了CT成像技术,对探测器进行平行光束探测效率的MC模拟,使建模更精确。模拟结果显示,探测效率曲线在11.0 ke V处会出现吸收边,是因为Ge元素被激发产生Kα、Kβ特征X射线发生逃逸,未被记录下来形成逃逸峰所致,这与实际实验情况相符。

122—1400keV能区同轴Ge(Li)和HpGe探测器效率曲线的函数拟合

在能量为122—1400keV范围内最优化方法用于四参数表达式ε=(a_1/E)^(a_2)+a_3Exp(-a_4E)和实验测定的同轴Ge(Li)和HpGe探测器效率的拟合。给出了初值计算方法。拟合结果是好的,实验和拟合值之间平均偏离小于2.0％。

HPGe探测器对圆形面源探测效率的研究

实验刻度了GEM60P4型高纯锗(High Purity Germanium,HPGe)探测器在H=250mm处对三种圆形面源(φ24 mm、φ80 mm和φ90 mm)的峰探测效率,结果表明,这三种源的效率基本一致。采用MCNP模拟了φ40–160mm内的圆形面源效率,研究了探测效率随样品直径的变化关系,并采用Geant4计算了圆形面源对同轴探测器的有效立体角。对φ90mm以上的样品源,探测效率随源直径的增大在逐渐减小,且高能γ射线效率减小程度较快,需采用标准源进行效率刻度。

单能光子在HPGe探测器上的能量响应函数模拟

根据单能光子与探测器发生相互作用的原理,本文利用蒙卡方法(MC)模拟了系列单能光子在HPGe探测器上的能量响应曲线并提取曲线的特征数据,然后采用最小二乘法对提取的特征数据进行拟合,得到单能光子在该探测器上的能量响应曲线理论函数表达式,最后采用准单能γ源测量数据对理论表达式进行修正,确立了该响应函数随光子入射能量变化的修正函数表达式,为连续光子能谱解谱提供了依据。

HPGe测量连续硬X射线能谱的解谱方法研究

结合数值模拟得到的单能光子在HPGe探测器上能量响应函数,用改进的剥谱法对测量得到的连续硬X射线能谱进行解谱。扣除测量谱中康普顿、反散射等效应产生的计数对测量能谱的影响,得到了仅反映探测器对光电效应的能量响应的能谱。最后,通过效率修正,完成了测量谱到实际能谱的还原,为连续硬X射线能谱解析提供了可靠方法。

低本底反康普顿HPGe γ谱仪的调试

本文报道的低本底反康普顿ＨＰＧｅγ谱仪．ＨＰＧｅ探测器对￣（６０）Ｃｏ的１３３２ｋｅｖγ射线的相对探测效率为３８．３％．能量分辨率为１．７７ｋｅＶ。在阱型反符合屏蔽下．对放在探测器端面的￣（１３７）Ｃｓ点状薄膜源的峰康比可达６８５．８：１；测量时间１００ｍｉｎ．置信度９５％时．￣（１３７）Ｃｓ点源的最小判断限为１．１２ｘ１Ｏ￣（－４）Ｂｑ。在物质屏蔽和阶型反符合屏蔽下，在５０～２１５２．８ｋｅＶ能区的积分本底为０．３４３ｓ￣（－１）。与无反符合屏蔽时相比，压缩系数大于４．５．对￣（１５２）Ｅｕ体源，谱仪积分非线性为０．０２７％。

MeV能区HPGeγ探测器本征效率和γ剂量的确定

使用多线γ放射源、氯化钠热中子俘获γ射线源、￣（１９）Ｆ（ｐ，αγ）源以及镍热中子俘获γ源来得到全能峰、单逃逸峰和双逃逸峰在７００－９０００ｋｅＶ能区范围内探测器本征效率值随能量变化的曲线。所得结果用来确定镍热中子俘获γ场，￣（１９）Ｆ（ｐ，αγ）反应γ场及反应堆重水循环系统上￣（１６）Ｏ（ｎ，ｐ）￣（１６）Ｎ反应γ场的γ剂量，并将其与用电离室测试的结果进行比较。