基于核物理虚拟仿真实验平台的γ能谱测量

利用核物理虚拟仿真实验平台,开展了γ能谱测量实验,标定了γ谱的能量刻度.实验测量了~(137)Cs和~(60)Co的背散射峰能量,实现了对未知射线能谱的测定,验证了能量与峰位道址的线性关系.基于虚拟仿真实验平台的核物理实验,灵活多变,操作性强,学生可自主设计实验.     

天文观察用超软X射线探测器的标定

在北京同步辐射装置3W1B光束线上,对天文观测用超软X射线(0.2keV—3.5keV)正比计数管探测器进行了系统地标定.得到了正比计数管的死时间、计数率坪曲线、能量线性、能量分辨、窗材料透过比曲线;借助于已标定过的光电二极管探测器,测量了正比管探测器的能量响应效率,标定不确定度在10%—18%之间.另外,还对正比管系统在卫星上的六道记录和在实验室里的多道记录进行了对比,两种记录方式符合得很好.     

不同厚度像素CdZnTe探测器的性能测试和评估

碲锌镉材料(CdZnTe)是目前探测X射线和γ射线的最好材料之一。将241 Am和137 Cs辐射源作用于像素CdZnTe探测器,通过实验和仿真分别得到能量谱估计、能量分辨率和峰值效率。由实验和仿真结果得出:在662keV的高能量下,厚度较大的CdZnTe探测器可获得更高的能量分辨率和峰值效率,但在59.5keV低能处会出现拖尾升高和电荷损失的现象;厚度较薄的探测器在低能处的特性反而更好。     

飞秒激光-固体靶相互作用中γ射线发射研究

采用137Cs-γ标准源对LiF热释光探测器进行了标定,将其用于测量激光-固体靶相互作用产生的γ射线的空间分布和能量分布。结果显示：γ射线主要在激光反射方向和靶法线方向附近区域发射;γ射线能量分布为类麦克斯韦分布,拟合的温度约为12.52 keV 。     

飞秒激光-固体靶相互作用中γ射线发射研究

采用137Cs-γ标准源对LiF热释光探测器进行了标定，将其用于测量激光-固体靶相互作用产生的γ射线的空间分布和能量分布。结果显示：γ射线主要在激光反射方向和靶法线方向附近区域发射；γ射线能量分布为类麦克斯韦分布，拟合的温度约为12.52 keV 。     

天文观察用超软X射线探测器的标定

在北京同步辐射装置3WlB光束线上,对天文观测用超软X射线(0.2keV-3．5keV)正比计数管探测器进行了系统地标定．得到了正比计数管的死时间、计数率坪曲线、能量线性、能量分辨、窗材料透过比曲线;借助于已标定过的光电二极管探测器,测量了正比管探到器的能量响应效率,标定不确定度在10％一18％之间．另外,还对正比管系统在卫星上的六道记录和在实验室里的多道记录进行了对比,两种记录方式符合得很好．     

强脉冲γ射线能谱测量仪研制北大核心

研制出了一种用于强脉冲γ射线能谱测量的能谱仪,在感应电压叠加器实验平台上,测量了阳极杆箍缩二极管产生的强脉冲γ射线能谱。选择适合强脉冲γ射线测量的Si-PIN探测器阵列和铅过滤片作为测量系统,通过在能谱仪的前部放置不同厚度的铅衰减片,测量了感应电压叠加器的强脉冲γ射线的强度。理论计算了不同能量的光子经过不同厚度的铅衰减片以后在探测器阵列上的能量沉积,得到了探测器的灵敏度曲线。利用探测器上的理论计算的电荷量和实验波形的对应关系,求解了该加速器的能谱。光子的最高能量约为1.44 MeV,平均能量为0.68 MeV,其中能量在0.4-0.8 MeV范围内的光子数最多,占74.3%。     

强脉冲γ射线能谱测量仪研制

研制出了一种用于强脉冲γ射线能谱测量的能谱仪,在感应电压叠加器实验平台上,测量了阳极杆箍缩二极管产生的强脉冲γ射线能谱。选择适合强脉冲γ射线测量的Si-PIN探测器阵列和铅过滤片作为测量系统,通过在能谱仪的前部放置不同厚度的铅衰减片,测量了感应电压叠加器的强脉冲γ射线的强度。理论计算了不同能量的光子经过不同厚度的铅衰减片以后在探测器阵列上的能量沉积,得到了探测器的灵敏度曲线。利用探测器上的理论计算的电荷量和实验波形的对应关系,求解了该加速器的能谱。光子的最高能量约为1.44 MeV,平均能量为0.68 MeV,其中能量在0.4~0.8 MeV范围内的光子数最多,占74.3%。     

高能量γ射线刻度源装置

在核物理实验和γ剂量探测中,γ射线探测器,如 Ge(Li),HpGe,Nal(T1)和 BGO等都需要刻度能量线性和相对效率.在兆电子伏能区,在加速器上可以利用不同的核反应获得不同能量γ射线.但在没有加速器的地方则无法进行.我们利用一个～105中子/s的Am-Be中子源制成了高能量γ射线刻度源装置.实验装置见图1.这个装置简单、方便.对于没有加速器的地方尤为实用. 一个原子核俘获一个热中子后,由于中子结合能,复合核将处在较高的激发态,它在退激时放出特征的单色γ射线,其能量由激发态的能级决定.一般来说,俘获γ射线谱是多线结构的,但是在高能部分,…     

ST-401薄塑料闪烁体中子能量响应测量技术研究

利用中国原子能科学研究院核工业放射性计量测试中心的5SDH-2串列加速器进行了ST-401薄塑料闪烁体的能量响应实验.选用T(p,n)³He反应和D(d,n)³He反应作为中子源，子源，中子束流采用复合屏蔽体进行准直，源强采用正比计数管和半导体望远镜进行监测，实验测量了厚度从0.16mm到2.00mm的八种规格薄闪烁体的能量响应曲线，对实验的结果的不确定度进行了分析.结果表明探测器的灵敏度随着晶体厚度的增加而增加，对于一定厚度的薄闪烁体，随着中子能量的增加，探测器的能量响应曲线坡度不大. 关键词： 塑料闪烁体 能量响应 正比计数器 半导体反冲质子望远镜     

Use of the EUR LiB 15/5 data set for radiation shielding calculations in iron

Abstract

The shielding effect of an iron sphere assembly has been tested for a Pu-α-Be neutron source placed in the center of the shield assembly. Emergent neutron and gamma spectra were measured with a stilbene scintillation counter. Discrimination between neutrons and gammas was achieved by the pulse shape discrimination technique based on the zero crossing method. Calculations have been made using the one-dimensional transport code ANISN-Westinghouse version (ANISN-W) and the EUR LiB 15/5 cross section data set. The agreement between measurements and calculations indicates that the cross section set and the calculation model are suitable for studying the iron shielding experiments over the neutron energy range 1.35–10 MeV and the gamma energy range 0.3–6 MeV. Total macroscopic cross sections for fast neutrons, linear attenuation coefficients for gamma rays and half-value thicknesses for neutrons and gammas for the whole energy range and at different energies have been obtained.     

Optimum condition of efficiency functions for HPGe γ-ray detectors in the 121-1408 keV energy range

The optimum condition of three commonly used functions in the Genie 2000 γ spectra analysis software have been studied in the 121-1408 keV energy range.The three functions are applied for fitting the full-energy peak effciency of the HPGe gammaray detector.A detailed procedure to obtain the optimum condition is described.The HPGe detector is calibrated at 11 cm by three radioactive sources of point form(152Eu,137Cs,60Co) providing 11 energy peaks.After data processing,results shows that the three functions used in the Genie 2000 gamma spectra analysis software fit best at orders 3-5.Lastly the standard radioactive source 133Ba is chosen to validate the results.Differences between the standard activity of 133Ba and the result obtained from the fitting functions are below 1.5%.Therefore the optimum orders of the three functions used in the Genie 2000 γ spectra analysis software are 3-5 with the 11 energy peaks.     

Neutron and high-energy gamma-ray emission in 12C Induced reactions on 159Tb

The gamma-ray multiplicity associated with the emission of high-energy gamma rays and neutrons following ¹²C+¹⁵⁹Tb reactions at E_lab= 100 MeV has been measured. The spin decrease deduced for coincident gamma rays within the GDR energy region is found to be in agreement with an estimate based on a statistical model. Neutron spectra measured in coincidence with high-energy gamma rays are explained in terms of two components. The cooler component corresponds to neutrons evaporated from the compound nucleus. The hotter component emanates from a precompound source moving in the center-of-mass system along the beam direction. The multiplicity of gamma-ray cascades, coincident with neutrons from the two different sources, has been deduced. The results show that beside the GDR there appears to be a second source of gamma rays with E_γ≈10MeV. These gamma rays are emitted in more peripheral reactions and before neutron evaporation.     

Implementation of a preamplifier-amplifier system for radiation detectors used in Mössbauer spectroscopy

We report the assembly and testing of a preamplification and amplification system for pulses produced by gaseous radiation detectors commonly used in Mössbauer spectroscopy. The system is composed by a pair of commercial integrated circuits A203 and A206, which operate as charge sensitive preamplifier-shaping amplifier and linear amplifier-low level discriminator, respectively. The integrated circuits were interconnected in the unipolar output mode and placed inside a metallic shielding, which prevents noise amplification for a suitable signal-noise ratio. The system was tested by irradiating a proportional counter LND-45431 with characteristic X rays of 6.3 keV and gamma rays of 14.4 keV emitted by a Mössbauer radioactive source of ⁵⁷Co (Rh). Unipolar pulses with Gaussian profile were obtained at the output of the linear amplifier, whose amplitudes were close to 0.4 V for 6.3 keV X rays and 1.4 V for 14.4 keV gamma rays. Pulse height spectra showed that the system allows a satisfactory identification of the X-rays and gamma rays emitted by the ⁵⁷Co source, giving the possibility to make a good selection of the 14.4 keV peak for having a suitable signal-noise ratio in the Mössbauer spectra. Absorption percentages of 14 % were found by taking the Mössbauer spectra of a natural iron absorber. The assembly and tests of the system are presented through this paper.     

Unfolding the fast neutron spectra of a BC501A liquid scintillation detector using GRAVEL method

Accurate knowledge of the neutron energy spectra is useful in basic research and applications. The overall procedure of measuring and unfolding the fast neutron energy spectra with BC501A liquid scintillation detector is described. The recoil proton spectrum of 241Am-Be neutrons was obtained experimentally. With the NRESP7 code, the response matrix of detector was simulated. Combining the recoil proton spectrum and response matrix, the unfolding of neutron spectra was performed by GRAVEL iterative algorithm. A MatLab program based on the GRAVEL method was developed. The continuous neutron spectrum of ²⁴¹Am-Be source and monoenergetic neutron spectrum of D-T source have been unfolded successfully and are in good agreement with their standard reference spectra. The unfolded ²⁴¹Am-Be spectrum are more accurate than the spectra unfolded by artificial neural networks in recent years.     

Comparison of Lu3Al5O12:Pr and Bi4Ge3O12 scintillators for gamma-ray detection

The scintillation properties of Lu₃Al₅O₁₂:Pr³⁺ (LuAG:Pr) single crystal grown by the Czochralski method with praseodymium concentration of 0.19 mol% were investigated. For a comparison, a good quality Bi₄Ge₃O₁₂ (BGO) single crystal grown by Bridgman method was also studied. The light yield and energy resolution were measured using photomultiplier tube (XP5200B PMT) readout. Moderate light yield of 15,900 photons per MeV was measured for the LuAG:Pr(0.19%) crystal. For 662 keV gamma rays (¹³⁷Cs source), an energy resolution of 6.5% obtained for LuAG:Pr(0.19%) is much better than that of 9.0% obtained for BGO. The light yield non-proportionality and energy resolution versus energy of gamma rays were measured and the intrinsic resolution of the crystals was determined after correcting the measured energy resolution for PMT statistics. The LuAG:Pr(0.19%) showed a good proportionality of the light yield within 5% over the energy range from 1274.5 keV down to 32 keV, which is much better than that of 14% for BGO. The photofraction was determined at 320 and 662 keV for both crystals and compared with the ratio of the cross-sections for the photoelectric effect to the total one calculated using WinXCOM program.     

Experimental calculations of number,energy and dose albedos for various materials using 662 keV gamma rays

ABSTRACT

Number, energy and dose albedos are measured at a scattering angle of 180° for a broad beam of 662 keV gamma rays obtained from a radioactive source of ¹³⁷Cs (having strength in µCi; 1 Ci?=?3.7?×?10¹⁰ disintegrations per second). The gamma beam is incident on semi-infinite thick targets of variable atomic numbers. The scattering media is divided into three sets, which are pure elements, alloys and composite materials. Experiments are carried out using a 3^″?×?3^″ NaI(Tl) scintillation detector. To obtain precision in data, the response unfolding of a scintillation detector is used, which converts the observed pulse-height distribution to a true photon spectrum over the energy range of 2.5 to 640 keV. The detector response unfolding results in the true intensity of back-scattered gamma flux by shifting the events resulting from partial absorption of photons to the full energy peak of the spectrum. In the present study, albedo factors are studied as a function of target thickness and their atomic number. The experimentally calculated numbers of back-scattered gamma photon are in good agreement with theoretically generated numbers of multiple back-scattered counts by using a Monte Carlo simulation code. The experimental data on energy and intensity of 662 keV gamma photons are used to evaluate the number, energy and dose albedos for different materials under investigation.     

基于CdZnTe像素阵列探测技术的伽玛源成像

根据高能射线针孔成像理论,采用CdZnTe像素阵列探测器建立了直接成像探测模式的伽玛源针孔探测系统。测试分析了CdZnTe像素阵列探测器的能量分辨力及峰值效率,讨论研究了针孔成像探测系统的调制传递函数和附加噪声特性,测试获得直径5mm137Cs源的探测图像,采用Lucy-Richardson迭代算法得到了137Cs源的复原图像。实验结果表明:CdZnTe探测器对662keV137Cs源的能量分辨力为6.25%～7.50%,峰值效率65.0%～72.5%;成像系统探测图像存在一定扩散现象,所采用的Lucy-Richardson迭代复原算法能较好地修正图像扩散,提高探测图像中心区域细节分辨力;估算所得137Cs源尺寸误差约0.5mm,所建立的CdZnTe针孔成像探测系统能有效得到小尺寸伽玛源的辐照强度分布及尺寸信息。     

Messung einiger (n, γ)-Spektren mit einem Paarspektrometer hoher Empfindlichkeit

A pairspectrometer of the 180°-focussing type with high efficiency and good resolution is described. The efficiency has been determined in function of the energy, both theoretically and experimentally and it is possible, therefore, to use this spectrometer for absolute calibration of gamma rays above 2·5 MeV. The evaluation methods of the pair spectra allow the single line to be determined with an error as little as ±8 keV (from 2·5 to 9 MeV). We have measured the neutron capture gamma spectrum of J¹²⁷, Cs¹³³, Ir^191,193, Bi²⁰⁰ and given the energy and intensity of the resolved gamma rays. From these results it is possible to compute the binding energy of the last neutron and also some unknown levels. The experiments, which have been performed in connection with the pairspectrometer, have shown an interesting possibility for research work with reactors. With an appropriate experimental arrangement and some special neutron capture gamma spectra, monochromatic gamma rays in the energy range between 3 and 11 MeV are obtained, which are better and much more intense as corresponding gamma rays from (p, γ) reactions.     

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。