基于虚拟点探测器的虚拟点源效率刻度技术

主要针对尺寸为ϕ75 mm×25 mm的²⁴¹Am标准体源HPGe探测器探测效率展开研究,通过LabSOCS软件模拟及蒙卡计算研究发现,使用同一种结构类型的探测器测量特定形状的体源,其虚拟点探测器位置与虚拟点源位置满足线性、二次函数、指数等关系。针对确定的探测器,通过点源在对称轴线上不同高度位置实验就可以标定出虚拟点探测器位置,再结合它们的线性函数进一步计算出虚拟点源位置,最后将点源放置于虚拟点位置刻度即可得到体源的探测效率。因此,该技术方法首次提出通过虚拟点探测器位置找到了虚拟点源的位置,是一种全新的刻度方法,已达到实际应用的程度,可以大面积推广应用该技术成果。     

Neutrons produced by muons in the LVD matter

The calculation results on the production, transport, and capture of neutrons produced by muons passing through the LVD are presented. The calculations are performed using the Monte Carlo transport codes GEANT4 and SHIELD. The efficiency of detecting the neutrons produced in both the scintillator and the detector’s structure is determined.     

积分中值定理在放射性氙样品γ谱效率刻度技术中的应用

在实验室HPGe探测器测量分析氙气样品过程中需要用到相对方法进行分析, 然而由于放射性氙同位素半衰期较短, 制作相应的标准气体比较难, 给谱仪系统刻度带来困难.针对该问题, 提出使用混合面源模拟刻度四种氙同位素气体源的效率, 并提出将积分中值定理应用到面源刻度实验过程, 大大简化了中间流程, 提高了测量的准确性.利用氙分离纯化系统在高氡环境下采集样品, 获得了天然放射性¹³³Xe气体γ谱, 通过计算得到其活度浓度. 积分中值位置处的混合面源刻度结果和气体源刻度结果一致, 说明本文提出的面源刻度技术及积分中值定理的思想在HPGe 探测器效率刻度测量分析中是有效可行的. 关键词： 面源 无源效率刻度软件 效率刻度     

井型高纯锗探测器体源样品无源效率刻度

采用蒙特卡罗程序MCNP建立物理模型,对井型高纯锗探测器的效率进行虚拟刻度。模拟计算在密度为0.4,1.2 gcm-3的6种不同成分环境样品中,探测器对射线的探测效率,当能量高于0.10 MeV时,体源样品的探测效率主要与样品密度、射线能量相关。以土壤、水和植物油样品为代表,结合所选取的函数模型,确定了密度范围0.1~1.6 gcm-3的固体源、密度1.0 gcm-3的水溶液和密度0.92 gcm-3的油溶液体源的效率函数及参数。实验采用标准源,对探测效率模拟结果进行了验证,探测效率的模拟值与实验值符合较好,二者误差均在3%以内。说明MCNP程序可以较为准确地模拟计算井型高纯锗探测器对射线的探测效率,验证了该无源效率刻度方法的准确性和可行性。     

基于放射性气体源体积的虚拟源刻度技术

大气中放射性气体氙同位素的活度浓度值是判断核裂变反应的关键数据, 长期以来其准确测量一直是个难题. 针对该问题, 本文提出和定义了虚拟点源的概念, 并使用LabSOCS软件模拟了不同尺寸气体体源和不同高度点源的探测效率, 根据计算的数据建立了气体源体积和虚拟点源位置的函数关系. 理论上证实了气体源体积和虚拟点位置有良好的线性关系, 在理论上为解决虚拟源刻度技术提供了新的途径.     

基于蒙特卡罗方法的几何因子计算程序

应用蒙特卡罗方法求解几何因子,基于蒙特卡罗方法的几何因子计算程序使用C++语言编写,可用于任意位姿的各种尺寸的圆面探测器对圆面源几何因子的计算。该程序使用了方差减小技巧。通过与国际通用蒙特卡罗计算程序（MCNP5）的计算结果对比,该方法具有结果准确（误差较小）、计算速度快、使用方便等优点。最终使用该程序计算几何因子,与实验数据进行对比,成功验证了中子深度分布分析（NDP）能谱测量系统探测器位姿的准确性（误差5%以内）,并对其移动位置进行修正,发现电机移动20 mm大约会产生1 mm的误差。     

Investigation of NaI(Tl)-Crystal Having Anomalous Inhomogeneity of Light Yield Spatial Distribution

An experiment with a layer-by-layer irradiation of the large volume NaI(Tl)-crystal has been performed. The inhomogeneity of the light yield spatial distribution along the crystal’s axis was revealed. A new method of accounting for the revealed inhomogeneity in the processing of the gamma-ray spectra registered using a crystal with nonuniform response is proposed. This method is quite universal: the conventional stages of the detector investigation (the calibration with standard gamma-ray sources and the inhomogeneity estimation using a layer-by-layer irradiation) are complemented by another one stage with computing of the absorbed energy distribution using Monte Carlo simulation. Finally, based on the results of these stages, the combined broadening function is formed for calculation of the response function.     

基于蒙特卡罗方法的几何因子计算程序

应用蒙特卡罗方法求解几何因子,基于蒙特卡罗方法的几何因子计算程序使用C++语言编写,可用于任意位姿的各种尺寸的圆面探测器对圆面源几何因子的计算。该程序使用了方差减小技巧。通过与国际通用蒙特卡罗计算程序(MCNP5)的计算结果对比,该方法具有结果准确(误差较小)、计算速度快、使用方便等优点。最终使用该程序计算几何因子,与实验数据进行对比,成功验证了中子深度分布分析(NDP)能谱测量系统探测器位姿的准确性(误差5%以内),并对其移动位置进行修正,发现电机移动20mm大约会产生1mm的误差。     

锂玻璃探测器中子探测效率的刻度

为了精确测量keV能区的中子俘获截面,中国原子能科学研究院正在建造一台4π 全吸收型γ 探测装置---GTAF,锂玻璃探测器将会作为中子束流监视器测量中子能谱。利用5SDH-2 加速器刻度了锂玻璃探测器在两个入射中子单能点(250 和565 keV) 的探测效率,并使用EANT4 和MCNP 程序模拟计算了锂玻璃探测器的相对探测效率。通过归一化实验数据和模拟结果,得到了锂玻璃探测器在10keV~1 MeV 能区的中子探测效率曲线。对于把锂玻璃探测器测量得到的飞行时间谱转化为中子束流能谱,是一项非常重要的工作,同时为探测器效率刻度提供了新方法。In order to accurately measure the neutron capture cross section in the energy range of keVMeV, 4 πgamma-ray total absorption facility (GTAF) is being constructed at China Institute of Atomic Energy (CIAE). The lithium glass detector will be used as a neutron beam monitor for GTAF. The detection efficiency of the lithium glass detector at two incident neutron energy points (250, 565 keV) was calibrated in 5SDH-2 accelerator, and the relative detection efficiency was simulated by GEANT4 and MCNP code. By the normalization of the experimental data and simulation result, the neutron detection efficiency curve of the lithium glass detector between 10 keV and 1 MeV was obtained. This work will be important to convert the Time-of-flight spectrum that be measured by Li-glass detector to the energy spectrum of neutron beam, and provide the new method for calibration of detection efficiency.     

Simulation study using GEANT4 Monte Carlo code for a Gd-coated resistive plate chamber as a thermal neutron detector

The Resistive Plate Chamber (RPC) has been developed in many application areas ever since its introduction, from high energy physics experiments to positron emission tomography. Such detectors can be coated with a Gd layer that enables them to detect thermal neutrons. Consequently these RPCs can be utilized for industrial and medical purposes. Here, we present the configuration of a resistive plate chamber which is utilized to detect thermal neutrons by employing GEANT4 Monte Carlo code. The response of the RPC was evaluated as a function of neutron energy in the GEANT4 Monte Carlo code. The simulation results are taken for incident neutron energy in the energy range from 25 meV to 100 meV. The detection efficiency was found to be between 10% and 20%, depending on the detector configuration, for incident thermal neutrons of 25 meV energy.     

基于蒙特卡罗方法的NaI探测器效率刻度及其测量轫致辐射实验

为了将NaI探测器更好地应用到轫致辐射谱测量工作中,对一套NaI探测器做了研究:利用~(137)Cs,~(60)Co等同位素γ源,结合蒙特卡罗方法,得到全能峰效率的模拟值与实验测量值符合得较好;利用蒙特卡罗N粒子编码模拟NaI对不同能量光子的响应,得到了该探测器对光子的能量响应,并将获得的能量响应用于轫致辐射的解谱工作,解谱结果与原始谱符合得很好;将该探测器应用到强流电子束打靶轫致辐射测量实验中,对轫致辐射在NaI探测器中的响应做了初步测量.     

基于虚拟刻度原理对放射性体源效率刻度方法的发展

采用蒙特卡罗模拟计算的方法,标定能够适用于不同HPGe探测器上的体源虚拟点源位置,需要对点源、体源的探测效率进行模拟计算。通过²⁴¹Am、¹³⁷Cs、⁶⁰Co点源和体源研究了HPGe晶体尺寸、类型对它们的虚拟点源位置的影响,模拟结果表明²⁴¹Am虚拟点源位置随着探测器尺寸、类型的不同呈现明显的差异性,说明虚拟刻度原理对于探测器表面的小体积样品测量在低能区间是不可取的,最后采用¹³⁷Cs、⁶⁰Co源得出体源高度与虚拟点源位置的半经验公式。通过实验室两台HPGe探测系统对尺寸Φ70 mm×65 mm标准土壤体源的探测效率进行计算,与模拟探测效率值、虚拟点源效率表征结果对比分析,验证了拟合一组表征虚拟点源位置的半经验公式是可行的。实验结果表明,对γ能量区间在300～2 000 keV进行体源的虚拟刻度时,选择可靠的定标源即可建立体源和虚拟点源位置的关系。这为解决监测工作中样品与探测器之间重复进行探测效率校准的问题提供了新的途径。     

Benchmark measurements and simulations of dose perturbations due to metallic spheres in proton beams

Monte Carlo simulations are increasingly used for dose calculations in proton therapy due to its inherent accuracy. However, dosimetric deviations have been found using Monte Carlo code when high density materials are present in the proton beamline. The purpose of this work was to quantify the magnitude of dose perturbation caused by metal objects. We did this by comparing measurements and Monte Carlo predictions of dose perturbations caused by the presence of small metal spheres in several clinical proton therapy beams as functions of proton beam range and drift space. Monte Carlo codes MCNPX, GEANT4 and Fast Dose Calculator (FDC) were used. Generally good agreement was found between measurements and Monte Carlo predictions, with the average difference within 5% and maximum difference within 17%. The modification of multiple Coulomb scattering model in MCNPX code yielded improvement in accuracy and provided the best overall agreement with measurements. Our results confirmed that Monte Carlo codes are well suited for predicting multiple Coulomb scattering in proton therapy beams when short drift spaces are involved.     

Study of the energy response of high pressure ionization chamber for high energy gamma-ray

The energy response calibration of the commonly used high pressure ionization chamber is very difficult to obtain when the gamma-ray energy is more than 3 MeV. In order to get the calibration of the higher part of the high pressure ionization chamber, we use the Fluka Monte Carlo program to perform the energy response in both the spherical and the cylindrical high pressure ionization chamber which are full of argon gas. The results compared with prior study when the gamma-ray energy is less than 1.25 MeV. Our result of Monte Carlo calculation shows agreement with those obtained by measurement within the uncertainty of the respective methods. The calculation of this study is significant for the high pressure ionization chamber to measure the high energy gamma-ray.     

充气反冲核谱仪焦平面探测阵列的GEANT4模拟

充气反冲核谱仪(SHANS)是目前国内合成缺中子锕系新核素、研究重核素a衰变性质的重要实验装置.为进一步提高焦平面探测阵列对重核素a衰变粒子和射线的探测效率,计划对现有探测装置进行升级.本文的主要工作是采用基于蒙特卡罗方法的GEANT4软件对现有的谱仪探测器阵列进行模拟,并与实验测量数据进行比较,以验证程序的准确性.结...     

Application of the Monte Carlo method for spectrometer calibration to determine the surface activity of radionuclides deposited on the ground

The results of efficiency calibration and verification of the in situ method with application of a handheld spectrometer with high-purity germanium detector are presented. The conducted studies show that the calibration of spectrometer efficiency with the use of the Monte Carlo method can be applied for measurement of the surface activity of radionuclides deposited on the ground with an uncertainty of not more than 22%.     

An application of the Monte Carlo method to determine an active volume of a semiconductor detector

A Monte Carlo model of scattering and absorption events of a gamma-ray in a finite detector is presented. For the effect of a finite detector to be included, energy spectra of scattered electrons are calculated using random sampling technique. This makes possible the accurate calculation of an active volume of a given semiconductor detector.     

Study of the energy response of high pressure ionization chamber for high energy gamma-ray

The energy response calibration of the commonly used high pressure ionization chamber is very difficult to obtain when the gamma-ray energy is more than 3 MeV.In order to get the calibration of the higher part of the high pressure ionization chamber,we use the Fluka Monte Carlo program to perfclrm the energy response in both the spherical and the cylindrical high pressure ionization chamber which are full of argon gas.The results compared with prior study when the gamma-ray energy is less than 1.25 MeV.Our result of Monte Carlo calculation shows agreement with those obtained by measurement within the uncertainty of the respective methods.The calculation of this study is significant for the high pressure ionization chamber to measure the high energy gamma-ray.     

Simulation of residual activity in steel and copper targets induced by 950 MeV/nucleon uranium ions

Radioactive nuclides will be produced in structures and surrounding materials of the relativistic heavy ion collider NICA. Predicting radioactivity in the materials, air, cooling water, and ground is an important part of the technical project. Some Monte Carlo transport codes (FLUKA, GEANT4, SHIELD) can simulate the production of radionuclides induced by heavy ions. The preliminary verification of MC codes with experimental data is necessary before using them for radiation protection purposes. In the present work, comparisons of the experiment and GEANT4 and SHIELD simulations of induced activity in thick stainless steel and copper targets irradiated with 950 MeV/nucleon uranium ions are presented.     

双维位置灵敏CsI(Tl)闪烁探测器

介绍了一种双维位置灵敏CsI(Tl)闪烁探测器, 利用GEANT4对它进行了蒙特卡罗模拟, 得到了RIB 17N的位置分布谱及探测器的空间位置分辨,　模拟结果与实验测量值很好地吻合。给出了影响探测器分辨的主要因素及改进方案。A two dimensional position sensitive CsI(Tl) scintillation detector readout with PSPMT was introduced. The performance of detector was simulated by using Monte Carlo code GEANT4. The position spectrum of RIB 17N and the detector’s position resolution were obtained, and the simulation results accorded with the experimental ones. The main factors, which can affect performance of the detector, and some planned detector improvements were presented.