硅半导体二重符合反冲质子望远镜

文章叙述半导体二重符合反冲质子望远镜的调试和在14MeV中子源上与伴随粒子法的比对测量。     

快中子能谱在线测量的反冲质子望远镜响应模拟研究

快中子能谱是基于散裂中子源开展大气中子单粒子效应研究的关键输入参数,在线测量宽能区快中子能谱在近散裂靶位置面临飞行时间法不确定度大、中子通量高、本底干扰强等问题。设计了反冲质子望远镜(RPT)系统,利用Geant4模拟了20～200 MeV中子轰击不同厚度聚乙烯转换靶产生的反冲质子产额、角分布以及能谱,为优化探测系统设计提供了指导依据。通过模拟硅探测器与新型快响应CLLB闪烁体组成的二重符合RPT系统对入射中子的响应,分析了影响探测系统探测效率和能量分辨率的因素,确定了聚乙烯转换靶厚度为1 mm、符合质子探测器摆放角度为26.6°和探测器尺寸等重要参数,得到了RPT系统的中子响应函数矩阵,并计算了其探测效率达10-5,对高中子通量和复杂本底干扰环境下的快中子能谱在线测量具有指导意义和参考价值。     

中子通量测量的质子反冲望远镜

研制了用于测量D-T中子通量的质子反冲闪烁望远镜,望远镜由二个对带电粒子响应的半导体探测器(△E)和一个CsI(TI)闪烁探测器(E)组成.利用脉冲形状甄别技术抑制CsI闪烁探测器的γ射线本底,△E探测器的高偏压对提高信噪比是重要的.二个△E探测器和一个E探测器实现了三重符合.在三重符合条件下,通过有、无辐射体的测量得...     

反冲质子望远镜效率计算中的相对论修正

反冲质子望远镜和伴随粒子法是绝对测量14 MeV单能快中子通量的两种独立的方法,在高压倍加器上利用T(d,n)~4He反应可以获得14 McV单能快中子。反冲质子望远镜是通过中子入射在聚乙烯辐射体上产生反冲质子,用记录反冲质子数来确定中子通量的,而伴随粒子法则是通过记录α粒子数来测定中子通量。随着14 MeV单能快中子的应用越     

强流D-T中子发生器n-γ辐射场的MC模拟研究

根据D-T中子源260 keV氘束流能量下的中子能谱和角分布数据,建立了D-T中子源模型,在中子发生器各元件材料及实验大厅墙壁对快中子的慢化、散射和吸收的条件下,采用MCNP模拟程序对强流中子发生器n-γ辐射场进行了模拟研究,得到了中子能谱、中子和γ角分布、n-γ比等重要参数.模拟结果与有关文献实验数据的基本吻合,验证了所建立的MCNP模拟模型的可靠合理.     

反冲质子谱的计算模拟及氢深度分布的研究

本文介绍了一种弹性反冲探测分析冲质子谱模拟的计算方法。用这种方法对４０ｋｅＶ质子注入硅中和非晶硅薄膜中氢浓度的深度分布进行了研究，并取得了良好的结果。     

固体反冲质子辐射转换体THGEM快中子探测器特性模拟研究

使用Geant4模拟研究了基于聚乙烯辐射转换材料的THGEM快中子探测器的辐射转换特性。结果表明,探测器响应具有一定阈特性,其灵敏度、响应阈值随辐射体厚度、吸收层厚度、中子入射角度、辐射体面积变化而改变。中子垂直入射,聚乙烯辐射体厚度50μm、铝吸收层厚度10μm时,探测器阈上响应具有较好的坪特性,阈值为2.2 MeV,灵敏度为1.0×10-4cm2。     

反冲质子磁分析技术的研究进展

反冲质子磁分析技术作为探测聚变中子能谱的新技术,具有能量分辨率和信噪比高的优点,适合混合干扰和宽量程中子注量率条件下的测量,已经成为聚变装置中子诊断的重要手段.介绍了国际上几个大科学装置研制的反冲质子磁分析谱仪和实验结果,磁质子反冲谱仪(MPR),磁分析系统使用两块分离的电磁铁,能量分辨率达2.5％;磁反冲谱仪(MRS...     

D-T快中子照相准直屏蔽体设计及中子束特性的模拟研究

设计一个用于氘氚(D-T)快中子照相的准直屏蔽体系统,对D-T中子发生器快中子在准直屏蔽体材料中输运的MCNP模拟研究,给出准直中子束的中子能谱、注量率及均匀性、γ射线能谱和γ射线注量率等重要参数.模拟结果显示,用D-T中子发生器中子源和合理的准直屏蔽体系统可得到快中子照相所需的准直快中子束.     

D-T中子照射下含硼聚乙烯球泄漏γ能谱测量

为了更清楚地了解含硼聚乙烯的屏蔽性能,用反冲电子法测量了D T中子照射下的不同B4C含量的聚乙烯球的泄漏γ能谱,并用MCNP/4A程序和ENDF/BⅤ库数据进行模拟计算。实验测量值和计算值在误差范围内符合得较好。     

Measurement of neutron spectra through composed material block bombarded with D-T neutrons

A 2-dimensional composed material assembly made of the iron and hydric block has been established. The neutron spectra from the assembly bombarded with 14-MeV neutrons at neutron generator have been obtained using the proton recoil technique with a stillbene detector. The detector positions were selected at the 60°, 120°, 180° on the surface of the iron spherical shell. The background neutron spectra consisted of background and room return radiation were subtracted with combination of methods of experimental shielding and MCNP calculation. The uncertainty of results was 6.3-7.4%. The experiment results were analyzed and simulated by MCNP code and two data library. The difference is integral neutron flux (background neutron subtracted) of measured results greater than calculations with maximum of 21.2% in the range of 1-16 MeV.     

Neutronics analysis of a stacked structure for a subcritical system with LEU solution driven by a D-T neutron source for 99Mo production

The utilization of neutrons markedly affects the medical isotope yield of a subcritical system driven by an external D-T neutron source.The general methods to improve the utilization of neutrons include moderating,multiplying,and reflecting neutrons,which ignores the use of neutrons that backscatter to the source direction.In this study,a stacked structure was formed by assembling the multiplier and the low-enriched uranium solution to enable the full use of neutrons that backscatter to the source direction and further improve the utilization of neutrons.A model based on SuperMC was used to evaluate the neu-tronics and safety behavior of the subcritical system,such as the neutron effective multiplication factor,neutron energy spectrum,medical isotope yield,and heat deposi-tion.Based on the calculation results,when the intensity of the neutron source was 5×1013 n/s,the optimized design with a stacked structure could increase the yield of 99Mo to 182 Ci/day,which is approximately 16％higher than that obtained with a single-layer structure.The inlet H2O coolant velocity of 1.0 m/s and initial temperature of 20℃were also found to be sufficient to prevent boiling of the fuel solution.     

Geant4 simulation of 238U(n,f) reaction induced by D-T neutron source

Knowledge of actinides(n,f) fission process induced by neutron is of importance in the field of nuclear power and nuclear engineering,especially for reactor applications.In this work,fission characteristics of~(238)U(n,f) reaction induced by D-T neutron source were simulated with Geant4 code from multiple perspectives,including the fission production yields,total nubar,kinetic energy distribution,fission neutron spectrum and cumulative γ-ray spectrum of the fission products.The simulation results agree well with the experimental nuclear reaction data(EXFOR) and evaluated nuclear data(ENDF).Mainly,this work was to examine the rationality of the parametric nuclear fission model in Geant4 and to direct our future experimental measurements for the cumulative fission yields of ~(238)U(n,f) reaction.     

Design of the thermal neutron beam for neutron radiography at the Syrian MNSR

Neutron beam design was studied at the Syrian reactor (MNSR, 30 kW) with a view to generating thermal neutron beam in the vertical irradiation sites for neutron radiography. The design of the neutron collimator was performed using MCNP4C and the ENDF/B-V cross-section library. Thermal, epithermal and fast neutron energy ranges were selected as <0.4 eV, 0.4 eV–10 keV, >10 keV, respectively. To produce a good neutron beam quality, bismuth was used as photon filter. In this design, the L/D ratio of this facility had the value of 125. The thermal neutron flux at the beam exit was about 2.548 × 10⁵ n/cm² s. If such neutron beam were built into the Syrian MNSR many scientific applications would be available using the neutron radiography.     

Si-PIN探测器中子直照灵敏度研究

介绍了利用K600中子发生器进行Si-PIN探测器灵敏度标定的实验方法,并在实验中测出了Si-PIN探测器对14MeV中子的直照灵敏度。同时,利用MCNP模拟程序对Si-PIN探测器不同能量的中子直照灵敏度进行了理论计算,实验灵敏度处理结果和理论计算值较为一致。     

基于光纤传输的中子发生器控制系统

叙述了基于光纤传输的中子发生器控制系统的工作原理、基本结构和技术性能，介绍了系统中部分硬件和主要软件，指出了开展进一步研制工作的方向。     

单球多计数器的中子能量响应计算

根据球体内随深度变化时中子的慢化程度有所差异．按两两垂直的方法把三个位置灵敏正比计数器安装在一个慢化球体内。用MCNP4A程序计算了6种慢化球体和6种照射方向的能量响应,同时对球半径方向两种分区方法的计算结果进行分析和比较。     

小型D-D中子发生器氘靶的热流固耦合分析

靶温对小型D-D中子发生器的使用寿命有重要影响,在假设束斑功率密度分布为高斯分布的前提下,使用ANSYS14.0软件对设计的小型D-D中子发生器的自成靶进行了热流固耦合分析。模拟了冷却水流量及冷却水层厚度对靶温的影响,同时模拟了两种不同结构的自成靶在束流轰击及冷却水共同作用下的应力及形变。模拟结果表明,两种结构的自成靶在使用中最高温度、最大应力与形变均满足设计要求。     

90°伴随粒子法D-D中子产额测量修正因子计算

开展了90°伴随粒子法D-D中子产额测量中的修正因子理论计算方法研究,基于MATLAB软件平台,开发了用于修正因子计算的计算机程序.计算给出了厚靶条件下,入射氘能量在20-700 keV范围,90°伴随粒子法D-D中子产额测量各向异性修正因子Rthick、中子和质子产额比(Yd,n/Yd,p)thick及总修正因子RY,并与早先的研究结果进行了对比,分析了计算结果的不确定度,总修正因子计算数据的不确定度约为2％.