BF3中子探测器阵列探测效率的蒙特卡罗计算

在用241Am-Be中子源对BF3中子探测器阵列探测效率标定的基础上,用蒙特卡罗方法对其探测效率进行了模拟计算,获得了比较满意的结果.然后用蒙特卡罗方法对BF3中子探测器阵列的探测效率进行了研究.研究结果表明,焦面探测器具有较好的探测效率.     

中子计数器探测效率的校准

设计制作了一个 BF3长硼中子计数器 ,采用伴随粒子法标定了其中子探测效率 ,约为 3.17×10 -4 ( 1± 18% )。利用这个中子探测器测量了中子管脉冲中子产额 ( 10 7/ pulse)     

BF3长计数器效率刻度及其应用

利用²³⁸U裂变反应，通过测量裂变碎块的数量，能够较为准确地测量快中子注量。但这种方法在中子能量为1.6MeV以下（裂变道未开或处于裂变截面第1个台阶上升处）和6.0～7.0MeV能区（第2个台阶上升处）由于不确定度过大而不适用。本工作采用4种不同的核反应作中子源，对北京大学4.5MV静电加速器中子实验大厅的BF₃长计数器的相对效率进行了刻度。将²³⁸U(n,f)反应与相对效率已知的BF₃长计数器相结合，解决了在上述能区准确测量中子注量的问题。      

Study of equivalent efficiency calibration method for radioactive gas source measured on HPGe detectors

ABSTRACT

In view of the complexity of current detection efficiency calibration of radioactive gas sources, a method using solid planar sources to be equivalent to gas sources was studied. For the 50 mL gas source box, an optimal equivalent scheme was selected by Monte Carlo Simulations. Then, the full-energy-peak efficiency curve of gas sources at the measurement position of 25 cm, with source-to-detector distance of 25 cm, was fitted by measuring solid planar sources with known activity. To verify the accuracy of the efficiency curve, ⁴¹Ar, ¹³³Xe and ⁸⁷Kr gases were produced and determined by length-compensated method. Then, their full-energy-peak efficiencies at 25 cm position away from the detector were directly calibrated. The percentage efficiency deviations between interpolation from the efficiency curve and direct calibration are all less than 2.5%, which proves the accuracy of the equivalent method. This calibration method is a general one and can be also used for some other radioactive sample measurements, such as non-destructive analysis of gaseous fission product samples with a suitable source-to-detector distance.     

利用BF_3多柱谱仪测量临界装置中子能谱

研发了一种中子能谱测量装置——BF_3多柱谱仪。对BF_3多柱谱仪的工作原理、结构与性能,以及该探测系统的使用方法进行研究,并分析其可满足的实验要求。应用BF_3多柱谱仪在临界装置上进行了中子能谱测量的实验,将实验测量结果与MCNP程序的理论计算结果进行了比较,两者符合较好,验证了该中子探测系统的性能。该BF_3多柱谱仪可适用于低中子通量密度能谱测量、屏蔽实验、环境监督测量、实验大厅内部及周围环境中子场测量等多种工况。     

MC法模拟电离室的空气等效材料

为保证放射治疗中绝对剂量验证更加快速、准确可靠,用MC法模拟γ光子在不同室壁材料电离室灵敏体积中的能量沉积,并经过计算得出不同室壁材料的能量响应曲线,同时研究了不同室壁厚度下电离室的能量响应曲线,比较得出与空气壁等效的室壁材料。使用空气等效材料可以提高绝对剂量验证中电离室的测量精度,此方法可作为绝对剂量验证中电离室室壁设计的参考。     

溴化镧探测器的晶体表征与全能峰效率计算

无源效率刻度技术已在辐射探测器的效率刻度中得到了广泛的应用。本文基于点源效率实验及蒙特卡罗模拟计算方法,对溴化镧探测器的晶体尺寸进行了调整;在此基础上,计算得到不同位置处全能峰效率的计算值。点源效率实验的验证结果表明,在121～1 332 keV能量范围内,γ光子全能峰效率的计算值与实验值的相对偏差小于±5%。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

HPXe电离室和LaCl3(Ce)探测器在核材料鉴别中的应用

在核材料鉴别中，鉴于铀、钚材料中同位素种类多，发射的多条γ射线能量比较集中（主要都在0．1～2MeV之间）且分支比都比较小，生成的γ能谱复杂等特点，对于测量铀、钚材料的γ探测器要求具有高的能量分辨本领和探测灵敏度。常用于该种测量的是NaI闪烁探测器和HPGe探测器，而新的高压氙（HPxe）电离室探测器和LaCl3（Ce）探测器为核材料的鉴别提供了一种新的有效检测手段。     

极大体积(>200cm~3)同轴HPGe探测器的研制及其特性

文章叙述了极大体积(～220cm~3)同轴HPGe探测器的研制及其性能。分析了各种因素对探测器系统分辨率的影响。探测器对~(60)Co的1.33MeVγ射线,能量分辨率FWHM=2.30±0.02keV,相对效率η=44.56%,峰对称性FW(1/10M)/FWHM=1.90;对2.60MeVγ射线,FWHM=3.10 keV。     

阵列BF3计数器制作与性能研究

设计和实验研制了用于脉冲中子源中子产额绝对测量的阵列BF3 计数器,并在加速器上进行了DT中子灵敏度标定实验。给出了该计数器测量DT脉冲中子产额的测量结果和测量不确定度,并与其它测量方法的测量结果进行了比较。实验验证了BF3 设计的可行性和DT脉冲中子产额测量数据的可靠性。     

Collimated LaBr3 detector response function in radioactivity analysis of nuclear waste drums

The properties of a Lanthanum bromide （LaBr3） detector and its response functions were investigated via experiments and simulations in this paper. The LaBr3 detector had good relative energy resolution and higher efficiency than a high-purity germanium detector. Monte Carlo and other numerical methods were used to calculate the efficiencies of a LaBr3 detector with a square collimation window. A model of the numerical method was established based on a pure geometric model that was consistent with the experimental situation. The results showed that the detector response functions calculated by these methods were in great agreement with experimental results.     

Experimental optimization of a landmine detection facility using PGNAA method

The optimum moderator geometry increases the performance of prompt gamma neutron activation analysis (PGNAA) method considerably. In this work an 241Am-Be source was used in the moderator geometry for detecting buried landmines by PGNAA method. Experiments were done to find the best moderator geometry for the moderated 241 Am-Be source, by replacing the mine with a neutron detector and counting the thermal neutron flux. The flux of thermal neutrons at the place of mine was used as a determining factor to introduce the best moderator geometry.     

长硼计数器测量脉冲中子的漏计数问题探讨

根据BF3的探测原理,中子在聚乙烯的输运过程及管内10B（n,）7Li反应机理,通过大量的测量实验,模拟出脉冲测量中BF3漏计数概率很小的边界条件,该测量方法适合目前脉冲中子装置中的中子产额测量。     

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％。     

三管TDCR猝灭效率曲线法测量液体闪烁源的活度

简述了利用三个匹配的光电倍增管构成的TDCR方法测量液体闪烁源的原理、方法。用一套已知活度的^14C（正十六烷）液体闪烁猝灭系列源对该方法作了验证。提出提高探测效率,减小外推误差的方法。编制了测量过程的计算机程序。     

蒙特卡罗方法计算用于低能光子测量的高纯锗探测器的效率

在内照射活体测量中,为了用蒙特卡罗方法计算探测器对光子尤其是低能光子的探测效率,需要对探测器准确建模。通过使用蒙特卡罗模拟计算和实验测量相结合的方法来准确确定低能光子高纯锗探测器晶体的死层厚度、半径和长度;结果表明使用此方法确定的晶体尺寸来模拟计算探测器效率,在17．5～662keV光子能量范围内,低能光子高纯锗探测器探测效率的模拟计算结果与实验结果比较,相对偏差平均小于1．0％,最大为3．2％。     

Partitioning to elastic and inelastic processes of the energy deposited by low energy ions in silicon detectors

The energy partitioning into elastic and ionization collisions for low energy ions (<200 keV) slowing down in silicon is important for the prediction of the detection efficiency of silicon detectors and the calculation of the damage induced by such ions in electronic devices. The partition factor calculated using Lindhard’s theory as well as the results extracted from TRIM calculations do not agree with recent experimental data of Funsten et al. for low energy ions. A new partition factor is calculated using Monte Carlo simulations based on a model which splits the inelastic losses into local and nonlocal modes. The calculated factor is in good agreement with existing experimental data and with molecular dynamic calculations. The calculated partition factor is expressed in a form convenient for different applications.     

溴化镧探测器效率计算及刻度实验

采用蒙特卡罗方法计算了不同尺寸溴化镧闪烁体的吸收效率以及峰总比曲线。采用137 Cs、60 Co、152 Eu三种点源对Φ50mm×10mm LaBr3:Ce探测器进行了效率刻度实验,低能段刻度实验结果与蒙特卡罗计算结果基本一致。将实验结果与计算结果相结合,给出了探测器对0~10MeVγ射线的全能峰效率曲线,并给出了相应的拟合公式。结果表明,对于实验条件有限的情况,采用模拟计算相对效率曲线再结合部分能点绝对刻度校准的方法可快速有效地得到探测器的效率曲线。     

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.