结构设计和磁场对狭缝式脉冲裂变中子探测器的n/γ分辨能力的影响

采用MCNP程序计算了狭缝式裂变中子探测器的结构设计和磁场对n/γ分辨能力的影响。根据探测系统对2 MeV中子的灵敏度,得到了系统的n/γ分辨参数。结果表明,未添加磁场偏转系统时,能够获得的n/γ分辨大于5,满足设计要求。添加磁场偏转系统后,n/γ分辨能力至少提高两个量级。     

狭缝式脉冲裂变中子靶室对γ的抑制能力

本文采用MCNP程序计算了狭缝式裂变中子探测系统的伽玛灵敏度。并根据探测系统对14MeV中子灵敏度的实测值,得到了系统n／γ分辨参数。满足了n／γ分辨能力大于5的设计要求。     

γ灵敏切伦科夫光纤阵列探测器的γ/n分辨能力研究

在脉冲辐射混合场(n,γ)中进行γ射线参数测量,要求探测器系统必须有很快的时间响应,还应有很高的γ/n分辨能力。本文详述了切伦科夫(Cherenkov)辐射原理,用蒙特卡罗软件MCNP模拟计算了γ、中子在不同光纤阵列材料中的能量沉积,根据计算结果选择铅玻璃作为光纤阵列切伦科夫辐射体,配合常聚甲基丙烯甲酯(polymethylmethacrylate,PMMA)塑料光纤光导传输,由光电倍增管转换为电信号输出,研制了一种γ灵敏切伦科夫铅玻璃光纤阵列探测器。在中国原子能科学研究院的600 k V高压倍加器上进行了14.1 MeV中子灵敏度实验,又在西北核技术研究所60Co源上完成了1.25 MeVγ灵敏度实验。实验数据与模拟结果推算得出的数据基本相符,表明该探测器系统具有较高的γ/n分辨能力,可满足在脉冲中子、γ辐射混合场中对γ射线参数测量的分辨能力要求。     

BC501液体闪烁体对n-γ及能量的分辨与其尺寸的关系

BC501液体闪烁体广泛应用于探测快中子，但测量伴随着很高的γ本底。为寻找具有较好的n-γ及能量分辨的BC501闪烁体，利用脉冲上升时间法，对几种不同尺寸的BC501闪烁体进行n-γ及能量分辨测量。在下阈0.75和1MeV下，分别测量了Am-Be中子源的n-γ分辨谱以及相同条件下的γ上升时间-幅度谱。测量了d-T中子源14MeV的反冲质子脉冲高度分布。对不同尺寸BC501闪烁体的n-γ及能量分辨进行了比较。实验表明，综合考虑n-γ和能量分辨，闪烁体的体积不应太大，长度应在保证效率的条件下适中选择。      

n-γ分辨应用于252Cf自发裂变中子飞行时间谱测量

使用液体闪烁体BC501作为快中子探测器，对应用脉冲上升时间法符合甄别^252Cf自发裂变中子飞行时间谱中的γ射线的效果进行研究。实验测量了γ射线和能量大于1MeV的^252Cf自发裂变中子的脉冲上升时间分辨谱，分辨优质因子M达到4．6。符合甄别了中子能量下阈分别为0．5、0．8和1MeV时的^252Cf自发裂变中子飞行时间谱中的7射线，与未符合时相比，γ甄别率在99．90％以上。     

液体闪烁探测器中子γ射线测量研究

液体闪烁体对中子的响应函数,利用O5S蒙特卡罗程序进行计算,γ射线响应函数利用MATHA蒙特卡罗程序进行计算。分别对液体闪烁探测器(n,γ)分辨品质测量、Am-Be中子源的中子谱和γ射线能谱的测量、铁球在D-T中子照射下泄漏中子和伴生γ射线能谱的测量、水球在D-T中子照射下泄漏中子和伴生γ射线能谱的测量等内容进行了介绍,并对结果进行了分析和讨论。     

液体闪烁探测器中子和γ射线测量研究

液体闪烁体对中子的响应函数,利用05S蒙特卡罗程序进行计算,γ射线响应函数利用MATHA蒙特卡罗程序进行计算。分别对液体闪烁探测器（n,γ）分辨品质测量、Am—Be中子源的中子谱和γ射线能谱的测量、铁球在D—T中子照射下泄漏中子和伴生γ射线能谱的测量、水球在D—T中子照射下泄漏中子和伴生γ射线能谱的测量等内容进行了介绍,并对结果进行了分析和讨论。     

掺钆高阻性板室热中子探测器的性能模拟

利用MCNP和Garfield程序模拟粒子与高阻性板室(RPC)热中子探测器的作用过程,计算出了转换体Gd2O3的最佳厚度和高阻性板室探测器对中子、γ的灵敏度,并得出了热中子和1.25 MeVγ与探测器作用产生的电子能谱。最终利用模拟数据给出了RPC热中子探测器的探测效率和时间分辨随电场、混合气体比例的变化规律,得到了最佳的电场强度和混合气体比例。     

一个CsI（T1）探测器脉冲形状分辨p、α和γ的电路

本文描述了一个用于（中子、带电粒子）核反应双微分截面测量中分辨ｐ、α和γ的脉冲形状电路的研制、性能测试。使用该电路，可以满意地分辨ｐ、α和γ。     

伴随粒子法测量T(d,n)4He中子源注量率中的本底处理

T(d，n)^4He反应单能中子源广泛应用于14MeV中子的各种物理实验。采用伴随粒子法测量中子注量率，用金硅面垒探测器测量α粒子，用1μm厚Al箔屏蔽散射的d束，经过各种条件下的调节，系统可很好地直接在能谱上分辨各种粒子，从而获得较高精度的中子注量率。     

A real-time neutron-gamma discriminator based on the support vector machine method for the time-of-fiight neutron spectrometer

A new neutron-gamma discriminator based on the support vector machine (SVM) method is proposed to improve the performance of the time-of-fiight neutron spectrometer. The neutron detector is an EJ-299-33 plastic scintillator with pulse-shape discrimination (PSD) property. The SVM algorithm is implemented in field programmable gate array (FPGA) to carry out the real-time sifting of neutrons in neutron-gamma mixed radiation fields. This study compares the ability of the pulse gradient analysis method and the SVM method. The results show that this SVM discriminator can provide a better discrimination accuracy of 99.1%. The accuracy and performance of the SVM discriminator based on FPGA have been evaluated in the experiments. It can get a figure of merit of 1.30.     

A real-time neutron-gamma discriminator based on the support vector machine method for the time-of-flight neutron spectrometer

A new neutron-gamma discriminator based on the support vector machine(SVM) method is proposed to improve the performance of the time-of-flight neutron spectrometer. The neutron detector is an EJ-299-33 plastic scintillator with pulse-shape discrimination(PSD) property. The SVM algorithm is implemented in field programmable gate array(FPGA) to carry out the real-time sifting of neutrons in neutron-gamma mixed radiation fields. This study compares the ability of the pulse gradient analysis method and the SVM method. The results show that this SVM discriminator can provide a better discrimination accuracy of 99.1%. The accuracy and performance of the SVM discriminator based on FPGA have been evaluated in the experiments. It can get a figure of merit of 1.30.     

北京正负电子对撞机(BEPCⅡ)束流注入区辐射场研究

北京正负电子对撞机(BEPCⅡ)正负电子束流注入阶段的束流损失,影响储存环束流注入区及防护区辐射场。本文利用束流损失监测系统(BLM系统)分析了束流注入阶段注入区束流损失的位置和束流损失率,并结合FLUKA软件模拟计算对撞实验模式下束流注入阶段注入区的辐射场。结果表明:注入阶段注入区及其下游束流损失明显;辐射场内粒子能谱情况是中子为宽能谱且各向同性,切割磁铁 (铁靶)出射蒸发谱峰窄,峰值约为0.9 MeV,直接发射谱不显著;真空管(铝靶)出射蒸发谱峰宽且直接发射谱显著,峰值分别为4 MeV和20 MeV;光子能谱峰窄且前向性明显,能量在5 MeV以下分布集中;中子与光子剂量率水平相当;注入阶段比非注入阶段剂量率高约2个数量级;对撞实验模式下,实验测量整个运行阶段储存环光子剂量率平均水平约为1 000 μSv/h,中子剂量率比光子剂量率低1个数量级。     

一个10ns脉冲束流传输系统

我所质子静电加速器头部切割的10ns脉冲束流经加速成0.5至2.5MeV后,传输进入中子厅,或由高频扫描板扫开,经Mobley磁铁压缩成1—2ns脉冲束流,或由Mobley磁铁偏转,在距磁铁出口1.54米处得到一横截面为圆形的束斑。它的半径为2mm,最大散角为5mrad。如图1所示,为了利用大液体闪烁探测器测量快中子俘获截面,一个10ns脉冲束流传输系统     

中子伽马测-测工艺确定剩余油饱和度

比较了在测-渗-测工艺中，中子伽马与中子寿命测井在确定产层剩余油饱和度和水淹层的异同点以及解释结果方面的一致性。结果表明，中子伽马测井能够代替中子寿命测井，并显示出仪器结构简单!稳定性好、造价和测井费用低、易于推广应用等优点。     

中子伽马测-渗-测工艺确定剩余油饱和度

比较了在测-渗-测工艺中,中子伽马与中子寿命测井在确定产层剩余油饱和度和水淹层的异同点以及解释结果方面的一致性。结果表明,中子伽马测井能够代替中子寿命测井,并显示出仪器结构简单、稳定性好、造价和测井费用低、易于推广应用等优点。     

Consideration about the Single-neutron Microbeam Facility

A conception of the single-neutron microbeam facility was put forward in this paper. The specific particle (e.g. H^ , ^2d^ or α ) bombarding a specific target can generate neutron, when the particle energy is more than a threshold (e.g., H^ energy is more than 2 MeV). And if the specific beam spot on the target is very small, the neutron beam along the direction of the specific beam spot will be very small too. If the neutron beam is weak and a neutron detector is mounted after the specific neutron collimator, the single- neutron will be obtained. Therefore, if the specific target and the neutron detector are installed after the proton accelerator and the microbeam system, the single-neutron microbeam will probably be obtained.     

Preliminary Experiments on Accelerator-Driven Subcritical Reactor with Pulsed Neutron Generator in Kyoto University Critical Assembly

A series of preliminary experiments on an accelerator-driven subcritical reactor (ADSR) with 14 MeV neutrons were conducted at Kyoto University Critical Assembly (KUCA) with the prospect of establishing a new neutron source for research. A critical assembly of a solid-moderated and -reflected core was combined with a Cockcroft-Walton-type accelerator. A neutron shield and a beam duct were installed in the reflector region for directing as large a number as possible of the high-energy 14MeV neutrons generated by deuteron-tritium (D-T) reactions to the fuel region, since the tritium target is located outside the core. And then, neutrons (14MeV) were injected into a subcritical system through a polyethylene reflector. The objectives of this paper are to investigate the neutron design accuracy of the ADSR with 14MeV neutrons and to examine experimentally the neutronic properties of the ADSR with 14MeV neutrons at KUCA. The reaction rate distribution and the neutron spectrum were measured by the foil activation method for investigating the neutronic properties of the ADSR with 14 MeV neutrons. The eigenvalue and fixed-source calculations were executed using a continuous-energy Monte Carlo calculation code MCNP-4C3 with ENDF/B-VI.2 for the subcriticality and the reaction rate distribution, respectively; the unfolding calculation was done using the SAND-II code coupled with JENDL Activation Cross Section File 96 for the neutron spectrum. The values of the calculated subcriticality and the reaction rate distribution were in good agreement with those of the experiments. The results of the experiments and the calculations demonstrated that the installation of the neutron shield and the beam duct was experimentally valid and that the MCNP-4C3 calculations were accurately carried out for analyzing the neutronic properties of the ADSR with 14MeV neutrons at KUCA.     

Evaluation of gamma-ray and neutron energy for area monitoring system in the IFMIF/EVEDA accelerator building

The engineering validation of the IFMIF/EVEDA prototype accelerator, up to 9 MeV by supplying the deuteron beam of 125 mA, will be performed at the BA site in Rokkasho. A design of this area monitoring system, comprising of Si semiconductors and ionization chambers for covering wide energy spectrum of gamma-rays and ³He counters for neutrons, is now in progress. To establish an applicability of this monitoring system, photon and neutron energies have to be suppressed to the detector ranges of 1.5 MeV and 15 MeV, respectively. For this purpose, the reduction of neutron and photon energies throughout shield of water in a beam dump and concrete layer is evaluated by PHITS code, using the experimental data of neutron source spectra. In this article, a similar model using the beam dump structure and the position with a degree of leaning for concrete wall in the accelerator vault is used, and their energy reduction including the air is evaluated. It is found that the neutron and photon flux are decreased by 10⁴-order by employing the local shields using concrete and polyethylene around beam dump, and the photon energy can be suppressed in the low energy.