塑料闪烁光纤在高能中子辐照下质子分布特性的数值模拟

 利用Geant4系统模拟了在高能中子照射下,塑料闪烁光纤中产生的反冲质子的分布特性,分析了入射中子能量分别为2,4,6,8 MeV时,产生的反冲质子能量和方向分布,给出了反冲质子在不同方向上的能量分布。结果表明:向前和向后出射的质子分布不对称;反冲质子的能量在零与入射中子能量之间连续地分布;接近垂直入射方向产生的质子数较多;入射中子能量越高,产生质子数越少;反冲质子的出射角度越小,其能量越大,即沿着入射中子方向的反冲质子能量较大,垂直入射方向的反冲质子能量较小。     

基于反角白光中子源次级质子的探测器标定

目前国内外的质子标定终端较少,且普遍为单能质子束流.基于中国散裂中子源的反角白光中子源的eV—200 MeV中子能量区间的白光中子束流,以及中子与氢的~1H(n, el)反应,可以获得宽能谱的能量连续次级质子.利用1 GSps采样率、12 bit的波形数字化获取系统采集探测器输出波形信号,通过对波形信号的分析,得到中子及反冲质子的飞行时间,进而得到反冲质子的动能.利用该方法得到的质子,为探测器质子标定等研究提供了新的研究平台.在该研究平台已经开展了带电粒子望远镜的标定实验.研究了CsI (Tl)探测器不同的信号读出方式对望远镜的DE-E二维谱、幅度-质子动能二维谱等粒子鉴别方法得到的粒子鉴别的效果,得到了较优的探测器信号读出方案.该研究为带电粒子望远镜的建设提供了实验依据,也说明了基于反角白光中子源的宽能谱质子标定的可行性.     

强辐射环境下高能脉冲裂变中子探测方法

在研究通道衰减、探测方法分离和探测器中子/射线本征分辨的基础上,研究了测量高能脉冲裂变中子数目的探测技术。基于电流型Si-PIN探测器,设计了减本底的背靠背探测结构,给出了测量强射线和低能散射中子干扰信号及有效扣除强辐射本底的实现方法,最终实现了高n/n和n/分辨测量和强裂变中子、射线混合场中的高能脉冲裂变中子数目探测,探测系统的信号/辐射本底比可达到10倍以上。     

聚变中子能谱测量系统脉冲中子灵敏度的实验研究

为多种复杂环境下的稳态和脉冲DT聚变中子能谱测量建立了一种灵敏度优化反冲质子磁谱仪. 使用成像板和同位素α源测量了谱仪的反冲质子能量-位置投影关系. 利用稳态加速器中子源平台、通过单粒子计数方法结合三维带电粒子输运程序模拟,研究了谱仪脉冲中子灵敏度能量响应. 通过高探测效率参数设置使谱仪对DT中子的探测效率达到2×10^-5 cm²水平,从而在较弱中子源上获得了较高统计精度实验数据. 程序模拟结果与谱仪α粒子刻度和DT中子标定实验结果取得了良好的一致性,可由此发展精细解谱技术,以提高脉冲中子能谱测量的灵敏度和能量分辨. 关键词： 聚变中子能谱 磁反冲质子 脉冲中子灵敏度 粒子输运     

利用252 Cf快裂变室测量BC501A液闪探测器的相对探测效率和响应函数

本文利用²⁵²Cf快裂变室和多参数数据采集系统,逐事例的同时记录了自发裂变中子和瞬发伽马的飞行时间(TOF),脉冲形状甄别(PSD)和反冲能量(RE,裂变中子是通过测量反冲质子;瞬发伽马是通过测量康普顿反冲电子)三维信息.详细介绍了通过离线数据分析完全扣除三维信息中的伽马事例贡献,以获得Φ50.8 mm×50.8 mm的BC501A液闪探测器的相对探测效率和响应函数的方法.在不通过探测器响应函数进行数据转换的条件下,利用中子的能量直接确定了中子的有效测量阈值.得到的中子 关键词： 252Cf快裂变室')" href="#">²⁵²Cf快裂变室 BC501A液闪探测器 相对探测效率 响应函数     

反冲质子磁分析技术用于氘氚中子能谱测量研究

介绍了一种基于反冲质子法和磁分析技术的氘氚聚变诊断方法, 适用于稳态及脉冲条件下的等离子体温度、燃料密度和中子产额的精确诊断. 设计了小型的原理性装置, 磁分析器使用高性能钕铁硼二极永磁铁, 焦平面上使用CR-39固体径迹探测器或PIN探测器测量质子位置分布. 使用²³⁹Pu α 源对磁分析器进行了实验标定, 建立了配套的模拟程序. 利用蒙特卡罗方法模拟分析了装置整体性能, 并在K-400加速器上进行了中子实验研究.     

CsI(Tl)晶体中反冲Cs和I核Quenching?Factor的测量

许多实验对用CsI(Tl)闪烁晶体作为探测器来寻找和探测暗物质的可行性进行了研究.本工作利用8MeV单能中子轰击CsI(Tl)晶体探测器来研究Cs核和I核的QuenchingFactor.在数据处理中,运用脉冲形状甄别(PSD)方法来分辨反冲核信号和本底信号.实验结果表明,在7keV到132keV的能区中,Quench ingFactor随着反冲核能量的减少而增加.在探测暗物质的实验中,这一性质对于CsI(Tl)晶体探测器获得较低的能量阈值是很有利的.     

高能质子束流强度绝对测量的二次电子补偿原理研究

高能质子入射到金属接收体表面诱发的二次电子直接影响束流强度的测量精度,如何消除二次电子影响是实现束流高精度测量的关键.根据高能带电粒子在金属表面诱发二次电子发射理论,对高能质子束流强度测量的二次电子补偿原理进行了研究,设计了二次电子补偿结构.采用三块金属极板构成的实验装置在高能质子源上开展实验研究,实验测得在中间极板上输出的电流与入射质子束流强度的比值小于0.7%,中间极板上二次电子得到补偿,验证了二次电子补偿原理的正确性.研究表明,采用设计的二次电子补偿结构对高能质子束流强度进行测量时二次电子贡献小于1%.     

二次电子发射对质子束流测量精度的影响

二次电子发射直接影响法拉第探测器测量质子束流的精度,减小或消除二次电子发射的影响是提高束流测量精度的关键。根据二次电子补偿原理设计了二次电子补偿型同轴法拉第探测器,实验发现探测器测量质子束流强度时不能完全实现二次电子补偿。为改进和完善探测器的设计,从理论上分析了补偿片未能完全消除二次电子对束流测量影响的原因,是由于补偿片前向发射二次电子数目大于收集极后向发射二次电子数目所致。为此设计了质子束穿过金属箔发射二次电子测量装置,测量得到能量为5~10MeV质子穿过10μm厚铜箔时前向与后向发射二次电子产额,验证了理论分析的正确性。     

4He闪烁裂变中子探测器时间响应

研制了可用于脉冲辐射场中子探测的4He闪烁裂变中子探测器,并对其时间响应进行了理论和实验研究。采用经验公式和蒙特卡罗方法模拟计算了不同厚度裂变靶产生的裂变碎片和不同能量中子产生的反冲4He核在4He气中的飞行时间,并依据卷积原理推导出探测器的时间响应计算公式。计算结果表明,探测器的波形上升时间约为19.5 ns,半高宽约31.0 ns。用ING-103型稠密等离子体聚焦装置(DPF)脉冲中子发生器对探测器的时间响应进行了实验测量,实验结果与理论值基本一致。     

Quasifree photoproduction of eta mesons off the neutron

Quasifree photoproduction of eta mesons off nucleons bound in the deuteron has been measured with the CBELSA/TAPS detector for incident photon energies up to 2.5 GeV at the Bonn ELSA accelerator. The eta mesons have been detected in coincidence with recoil protons and recoil neutrons, which allows a detailed comparison of the quasifree n(gamma,eta)n and p(gamma,eta)p reactions. The excitation function for eta production off the neutron shows a pronounced bumplike structure at W=1.68 GeV (E{gamma} approximately 1 GeV), which is absent for the proton.     

Monte Carlo calculation of CR-39 efficiency for fast neutron detection using a combination of MCNP and SRIM codes,and comparison with experimental results

The elastic scattering of light nuclei, especially hydrogen, is widely used for detection of fast neutrons. Fast neutrons have a few interactions in solid state nuclear track detectors (SSNTDs), such as CR-39. It has been shown that to increase the efficiency of detector, a radiator layer, e.g. polyethylene may be used. In this work, the optimum thickness of the radiator layer has been determined. Some different thicknesses of aluminium layers have been used as discriminators for which the efficiency of detector to Am–Be neutron source has been calculated. A program FTRAC has been developed for the calculation of the detection efficiency. This software determines the specifications of recoil protons (using PTRAC card of MCNP code) and also the kinematics of interactions. Transport of recoil protons has been carried out using SRIM Monte Carlo code. A good agreement have been shown between measurement and simulation results.     

Slow and fast neutron detection using bare CN-85 cellulose nitrate detectors

We report on the application of CN-85 cellulose nitrate track detectors to neutron dosimetry. CN-85 has the ability to register proton tracks and therefore can be used for neutron detection via neutron-induced recoil events within the detector matrix. The CN-85 detectors were used to study the distribution of the weakly moderated spallation neutrons, produced in the irradiation of an extended Pb-target with 1 GeV protons. The results obtained are compared with Monte Carlo simulations using the MCNPX-2.5.c code. The thermal and epithermal neutrons can also be detected by CN-85 detectors without the need for a neutron converter via the ¹⁴N(n, p)¹⁴C reaction, which has a positive Q-value of 626 keV.     

Investigation of the possibility of γ-background discrimination in a neutron spectrometer with a proportional counter of recoil protons

The possibility of expanding the range of neutron spectrum measurements to lower energies in fields of mixed n-γ radiation via separation of pulses from recoil protons and γ-induced electrons, using the proportional counter developed for neutron spectrometry at the All-Russia Research Institute of Experimental Physics, has been investigated. With the use of a digital oscilloscope, a data set on the shape of counter pulses under irradiation in a field of mixed n-γ radiation (²⁵²Cf) and in a field of γ rays (SOSGI-M set) has been obtained. Mathematical processing of the obtained data set showed a possibility of distinguishing pulses from recoil protons and electrons; hence, for the ²⁵²Cf source, the lower boundary of the neutron spectrometer operating range can be reduced to ≈80 keV.     

Possibilities of using synthetic polymers in nuclear emulsions for the dosimetry of fast neutrons

The study contains the results obtained in the process of the preparation and study of the properties of nuclear emulsion of a new type made especially for fast neutron dosimetry.Synthetic hydrophilic polymers were used for the preparation of the emulsion and the sensitivity to fast neutrons — by the detection of recoil protons — was increased by enriching the emulsion with elementary hydrogen and by the use of additive recoil proton radiators.The dosimetric results obtained with this emulsion are compared with the results achieved by various authors with the gelatine emulsions used up to now.     

From imaging to dosimetry: GEANT4-based study on the application of Medipix to neutron dosimetry

An application of Medipix2 using a newly developed segmented multiple thickness polyethylene (PE) converter for fast neutron detection is presented. The system has the ability to provide an energy independent response for the dose equivalent for fast neutrons. The application of weighting factors to each defined thickness of PE allows for a flattening of the response of the detector system for dosimetry applications. Six PE converter segments were applied, and their thicknesses and weighting factors were optimised to obtain the required energy independent detector response. The study performed by means of GEANT4. Its suitability for neutron dosimetry was studied with respect to a previously published work.     

介质型快中子探测器中子直照响应模拟研究

 介质型快中子探测器的中子直照响应对其设计和实际应用具有重要影响。利用Geant4编制Monte-Carlo模拟程序对此型探测器的中子直照响应进行了计算。模拟了探测器芯子常用材料在中子入射时带电重粒子的发射情况,发现电荷收集极、卡阈吸收片和后高压绝缘层材料的选择对中子直照响应特性有直接影响。在现有的以聚四氟乙烯为卡阈吸收片和后高压绝缘层材料的探测芯子中,直照响应给总的中子灵敏度带来约6%的贡献。提出了一种使用高电阻率石墨作为卡阈吸收片和后高压绝缘层材料的探测芯子的优化结构,可有效降低中子直照响应。     

Fast Neutron Sensitivity of TL Detectors using Proton Radiator Techniques

TL materials have a small intrinsic sensitivity for fast neutrons. In order to increase this sensitivity one uses hydrogen containing radiators giving recoil protons as a result of the neutron interaction. By combining the proton radiator technique with the use of TL detectors having various glow peaks with a different response to recoil protons an additional sensitivity yield can be reached. The paper deals with the calculation procedure for the (radiator) sensitivity component. For the LiF phosphors TLD-600 and TLD-700 calculated and experimentally determined fast neutron sensitivities are presented for the glow peaks V and VII. The results show that for accident dosimetry a sufficient agreement of the dedector response with the dose-to-fluence conversion factors is obtained.