中子小角散射讲座：第三讲 中子小角散射在材料科学中的应用

X射线小角散射在材料科学中是分析物质结构的重要手段之一[1].由于中子吸收截面小,所以中子小角散射可以采用较大的厚块样品.长波长的冷中子,既可以避免X射线结晶学中的双布拉格衍射,又可以在较小的散射矢量Q范围内研究中子散射强度的分布.某些近邻元素(如 Al,Mg等),对X射线的散射能力几乎一样,而它们的中子散射振幅则是无规的.所以,中于小角散射又特别适宜研究相邻元素合金中的分凝现象.中子具有磁矩,能与磁性物质相互作用,产生磁的小角散射. 这里应当强调指出,所谓“小角”,是指小的散射矢量值,大小范围约为 其中da为样品中结构单元间…     

FTO客体3m闪光照相的Monte Carlo研究

 研究了客体模型FTO的闪光照相系统X光输运过程，给出了直穿照射量、散射照射量、直散比、直穿照射量能谱、散射照射量能谱、直穿X光通量能谱和散射X光通量能谱在记录平面的空间分布。结果表明：后锥是照射量散射成分的主要来源，后锥照射量占总散射量97%；后锥也是造成散射的空间分布不均匀的主要器件，这一不均匀性高达58%。照相系统的最小直散比非常小，表明锥造成的散射已经严重地淹没了直穿（轫致辐射）信号。计算中使用高空间分辨率记录法进行分点，合成图像对吸收系数的复原结果与国外报道的结果相符。     

神光Ⅲ主机装置内爆中子和伽马辐射特性的数值模拟

采用三维中子-光子耦合输运蒙特卡罗程序JMCT,对神光Ⅲ主机靶场进行精细几何建模,使用该模型通过计算获得了DD内爆聚变中子及伽马射线在靶场环境的空间分布以及能谱和飞行时间谱。根据计算结果对散射中子和伽马射线的特性进行了讨论,并定量分析了散射中子噪声和伽马噪声分别对下散中子产额测量和高能X射线照相的影响。研究结果表明:必须进行有效的辐射屏蔽设计才能使下散中子产额测量和高能X射线照相的信噪比优于10。     

铜活化法诊断神光Ⅲ主机装置氘氚中子产额

介绍了铜活化诊断氘氚中子产额的测量原理,分析了62 Cu和64 Cu两种活化核素在符合测量中的贡献。针对不同范围内的中子产额测量,提出了系统灵敏度相对标定法和64 Cu活化核标定法。通过添加中子屏蔽锥测量了标定场所散射中子影响。计算评估了63 Cu(n,γ)64 Cu反应过程对活化测量的影响。在神光Ⅲ主机装置上,利用该系统测量了直接驱动氘氚中子产额。实验结果表明:氘氚中子产额在109~1013范围采用相对标定方法较为合适,64 Cu活化核的标定方法适用于1012~1016范围内产额测量。标定场所散射中子对灵敏度标定因子影响约0.4%。63 Cu俘获辐射反应在64 Cu活化核标定中贡献小于1%。目前神光Ⅲ主机装置直接驱动氘氚中子产额约8×1012。     

2GW功率下CFETR中子屏蔽的初步中子学研究

在中国聚变工程实验堆(CFETR)真空室最新设计尺寸下,利用蒙特卡洛中子输运程序(MCNP)建立一维中子学模型,在2GW 的聚变功率下进行了计算。分析了中子反射材料ZrH₂ 对中子的屏蔽效果,发现200mm 的反射层可以屏蔽94.3%的中子通量和94.9%的中子核热。研究CFETR 在运行10 个满功率年(FPY)和20FPY 后,对应不同中子壁载荷的最小屏蔽包层厚度。结果显示,装置运行10FPY 后中子壁载荷在1.0MW·m⁻²、1.5MW·m⁻²、 2.5MW·m⁻² 时所对应的最小屏蔽包层厚度分别为44cm、53cm、65cm;而在装置运行20FPY 后,则需要在径向方向更厚的屏蔽包层才能满足中子屏蔽要求。屏蔽包层的尺寸优化将为目前阶段的CFETR 先进包层设计提供参考。     

A=40—70偶中子核素光子穿透系数的关联现象

本文给出了在共振区光子穿透系数的表示式,这由三部份组成,分别对应复合核统计过程、复合核弹性散射道及非弹性散射道中的辐射退激过程.研究了在中子强度函数3s巨共振区13个偶中子核素的中子辐射俘获截面.中子能量范围为3MeV以下的共振区.结果表明,在同时考虑了统计和非统计过程后,可以解释实验测量的总俘获截面及γ能谱.     

5单元中子散射相机仿真研究

采用粒子输运程序MCNP与FORTRAN,MATLAB程序相结合,对一种5单元结构的中子散射相机原型进行了蒙特卡罗模拟,对252Cf裂变中子源进行了图像、能量的重建。结果表明:该相机的能量分辨力为9%左右,角分辨与闪烁体的体积有关;中子能量为2 MeV左右时,散射相机的探测效率达到最大值;源的距离、闪烁体尺寸、前后面板距离、事件数等对重建图像的分辨力都有不同程度的影响;散射相机可以获得裂变中子源的能谱形状,但系统的结构、探测阈值等会使能谱测量造成一定的偏差。该理论工作的结论可推广到由更多单元组成的散射相机中使用。     

神光Ⅲ主机装置内爆中子和伽马辐射特性的数值模拟北大核心CSCD

采用三维中子-光子耦合输运蒙特卡罗程序JMCT,对神光Ⅲ主机靶场进行精细几何建模,使用该模型通过计算获得了DD内爆聚变中子及伽马射线在靶场环境的空间分布以及能谱和飞行时间谱。根据计算结果对散射中子和伽马射线的特性进行了讨论,并定量分析了散射中子噪声和伽马噪声分别对下散中子产额测量和高能X射线照相的影响。研究结果表明:必须进行有效的辐射屏蔽设计才能使下散中子产额测量和高能X射线照相的信噪比优于10。     

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。     

中子小角散射讲座：第一讲中子小角散射

中子小角散射是通过分析长波长中子(0.2—2 nm左右)在小角度内的散射强度来研究大小在几十到几千埃范围内的物质结构的一种专门的测量技术. 现在我们考虑波长为 0.1—1nm的一束中子,通过准直,使其发散度尽可能在 10-2ad以下.当这样的中子束照射在一样品上时,穿透样品的中子束强度衰减,同时在透射束的周围(大约为5°以下的角度范围内),出现了强度连续变化的散射中子,并没有产生通常的中子衍射图案,这种现象称为中子小角散射.它能给出比中子波长大几十、几百乃至上千倍大的尺度上的有关物质结构的信息. 散射样品中散射密度的不均匀,会产生中子…     

2.45 MeV小型D-D中子管准直屏蔽结构设计

为获取小角度出射的单能中子源,采用蒙特卡罗软件对小型D-D中子管产生的能量为2.45 MeV的4立体角中子源进行了准直屏蔽结构设计。准直屏蔽结构分为准直器和捕获穴,准直器采用铁+含硼聚乙烯+铅的三层过滤结构,用于屏蔽照射野外杂散中子,捕获穴主要功能是增加反方向中子的弹性散射次数,从而降低出射束低能散射中子的比例。通过MCNP模拟得到了准直器各层材料的最佳厚度和出射孔尺寸以及捕获穴最佳结构。经验证,中子照射野处2.45 MeV的中子通量比照射野外大三个量级,中子照射野处低能中子通量比2.45 MeV的中子通量低一个量级,墙壁外总剂量率（中子+）在2.5 Gy/h以下。该研究对于小角度单能中子源的快速获取具有一定的实用价值,获取的中子源可用于中子剂量仪器有效性检验、中子监测仪性能测试等方面的研究。     

14MeV中子照相中散射中子对成像影响的Monte Carlo模拟

依据实验参数，建立了14MeV快中子照相的物理模型，并利用Monte Carlo方法对照相过程进行了模拟. 分析了经聚乙烯样品散射的中子对快中子图像的影响随样品与探测器间距及样品参数的变化. 计算结果表明，样品与探测器的距离d<5cm时，样品中的散射中子对图像的影响强烈依赖于d，而当d>20cm时，样品散射中子对图像的影响可忽略；当样品密度为3—5g/cm³时散射中子对图像的影响相对最大；样品宽度越大，图像中的散射成分越多，当宽度在3cm以上时散射成分的强度趋于饱和. 关键词： 14MeV中子 快中子照相 散射中子 Monte Carlo模拟     

Neutron detectors for scattering experiments at HANARO

Position sensitive detectors (PSD) measure the distribution of scattered neutrons and are essential tools for neutron scattering experiments. Various types of neutron detectors used at neutron diffractometers are conventional tube detectors, 1-D and 2-D PSDs. Korea Atomic Energy Research Institute (KAERI) has been developing various kinds of PSDs to improve the instrument performance and to develop new scattering instruments. Our development work is initiated with 1-D PSD for residual stress analysis spectrometer and finally the technology is extended to development of 2-D PSD with planar and curved geometry. All PSDs are based on multiwire grid assembly with delay line readout method for position encoding, as the response is faster than charge division method and enables higher count rate capability. Design details and operational characteristics of some of the PSDs developed, for application at neutron scattering instruments are presented.      

厚闪烁体内次级中子对快中子图像质量的影响研究

利用编制的快中子照相数值模拟程序(FNRSC)模拟计算了入射中子能量为14 MeV时,厚度5—300 mm闪烁体内次级中子对快中子图像质量的影响,结果表明闪烁体厚度d<50mm时,次级中子对图像的影响强烈依赖于闪烁体厚度,而当d>50 mm时,次级中子对图像的影响趋于饱和.将文献中利用蒙特卡罗中子-光子输运程序(MCNP)计算的次级中子对图像影响和文中计算结果进行了对比,给出了二者存在差异的主要原因：次级中子分布对入射中子空间分布的强烈依赖性;能量沉积和荧光输出这两种计算方法对 关键词： 14 MeV中子 快中子照相 次级中子 Monte Carlo模拟     

Investigation of fast neutron interaction with235U

The angular distribution of neutrons emitted by elastic, inelastic and fission processes on²³⁵U were measured at the incident neutron energies of 1.5, 1.9, 2.3, 4.0, 4.5, 5.0 and 5.5 MeV using nanosecond time-of-flight technique. The differential elastic scattering cross sections and their angular distributions at all the seven energies are presented. The total elastic scattering cross sections, angle and energy integrated cross sections for the inelastically scattered neutrons in energy bands of 200 keV, fission cross sections and the angular distributions of fission neutrons were extracted at 1.5, 1.9 and 2.3 MeV incident neutron energies. The energy distributions of the prompt fission neutrons and of the inelastically scattered neutrons are given at the incoming neutron energies of 1.5, 1.9 and 2.3 MeV; and the average fission neutron energies and the inelastic neutron evaporation temperatures were also evaluated at these energies.     

中子照相数值模拟与实验的对比

 介绍了热中子照相的MCNP数值模拟方法，模拟了300＃反应堆Maxwell谱热中子束穿透样品射到转换屏的过程，给出了热中子对铝、铅、铁、铜的穿透能力，分析了引起模拟与实验结果不同的原因。通过模拟得到了清晰的图像，对比数值模拟与在300#反应堆中子照相装置上的实验结果，数值模拟结果图像与实验结果图像非常相似；散射中子对图像的影响也符合相同的规律，随着样品与转换屏之间的距离的增大，散射中子对结果图像的影响越来越小，当样品与转换屏之间的距离为样品尺寸的2倍时可以忽略散射中子的影响。     

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.     

中子散射对快中子照相质量影响的分析

通过一内空的圆柱体模型，对在快中子照相时由样品引起的散射中子强度与样品形状和探测距离之间的关系进行模拟，并用^241Am—Be作中子源对散射中子的影响进行实验验证。结果表明，在快中子照相时，由样品引起的散射中子的强度与探测距离以及样品形状有关。对于同一样品，探测距离增加，散射中子的影响则降低。The relationships between intensities of scattered neutrons by specimens and their shapes and detecting distances have been simulated using a hollow cylinder model, and the results were validated by experiments of fast neutron imaging using ^241Am-Be neutron source. The results showed that the intensities of scattered neutrons are closely related to the detecting distances and sample＇ s shapes. The influences of scattered neutronns in fast neutron imaging will be reduced while detecting distances increased.     

Evaluation of neutron radiation field in carbon ion therapy

Carbon ions have significant advantages in tumor therapy because of their physical and biological properties. In view of the radiation protection, the safety of patients is the most important issue in therapy processes.Therefore, the effects of the secondary particles produced by the carbon ions in the tumor therapy should be carefully considered, especially for the neutrons. In the present work, the neutron radiation field induced by carbon ions was evaluated by using the FLUKA code. The simulated results of neutron energy spectra and neutron dose was found to be in good agreement with the experiment data. In addition, energy deposition of carbon ions and neutrons in tissue-like media was studied, it is found that the secondary neutron energy deposition is not expected to exceed 1% of the carbon ion energy deposition in a typical treatment.     

Measurement of the neutron spectrum of a Pu-C source with a liquid scintillator

The neutron response function for a BC501A liquid scintillator （LS） has been measured using a series of monoenergetic neutrons produced by the p-T reaction. The proton energies were chosen such as to produce neutrons in the energy range of 1 to 20 MeV. The principles of the technique of unfolding a neutron energy spectrum by using the measured neutron response function and the measured Pulse Height （PH） spectrum is briefly described. The PH spectrum of neutrons from the Pu-C source, which will be used for the calibration of the reactor antineutrino detectors for the Daya Bay neutrino experiment, was measured and analyzed to get the neutron energy spectrum. Simultaneously the neutron energy spectrum of an Am-Be source was measured and compared with other measurements as a check of the result for the Pu-C source. Finally, an error analysis and a discussion of the results are given.