铝材料及纯水泥圆柱壳体上高能中子反照系数测量

高能中子是指大于6MeV的中子。在组合装置上测量高能中子及铝材料和纯水泥圆柱壳体高能中子反照系数。组合装置由铁和慢化吸收材料组成，中子源是K-400中子发生器上的D-T聚变中子源。采用高阈能活化箔技术测量高能反照中子引起的绝对活化反应率。通过比较有无铝材料和纯水泥圆柱壳体的活化反应率测量结果，获得铝材料和纯水泥圆柱壳体的高能中子反照系数。     

中子学实验近期进展

文章作者采用核活化法和核裂变法实验研究了加速器D-T中子、D-D中子以及~(252)Cf自发裂变中子在纯水泥体上的反射中子,获得了反射中子引起的6种高阈能活化箔的活化反应率以及~(235)U(包镉)和~(238)U裂变反应率.采用反冲质子法测量了4种厚度(4.5,9,18,27cm)聚乙烯板的角度中子谱.获得了聚乙烯铁铍组合壳体内距装置中心0,9.7,12.8和17.3cm 4个位置1MeV以上的中子能谱.采用铝核素标准截面相对测量法,获得了~(175)Lu、~(89)Y核素的(n,2n)反应截面.文章还分析了实验的不确定度.     

介质型脉冲高能中子探测器

首次报道一种基于反冲质子法和高速带电粒子在物质表面引起二次电子发射的高能中子探测方法,研制成功的新一代强流脉冲高能中子探测器,即介质型脉冲高能中子探测器.与传统的强流脉冲中子探测器相比,该探测器对中子的探测及信号的传输过程是在介质中完成的,因而不需要真空和高压也可以正常工作,并具有多项优异的物理性能.该探测器的输出信号来自于高能中子在聚乙烯转换靶产生的高能反冲质子和这些质子穿越电荷收集极表面时产生的部分二次电子.选择适当的卡阈吸收片和电荷收集极材料,二次电子在探测灵敏度中的份额及其随能量的变化可由实验测定.     

中国散裂中子源反角白光中子束流参数的初步测量

中国散裂中子源(CSNS)已于2018年5月建设完工,随后进行了试运行.其中的反角白光中子束线(Back-n)可用于中子核数据测量、中子物理研究和核技术应用等多方面的实验.本文报道对该中子束的品质参数测量实验过程以及最终实验结果.实验主要采用中子飞行时间法,利用~(235)U,~(238)U裂变室和~6Li-Si探测器测量了中子能谱和中子注量率,又利用闪烁体-互补金属氧化物半导体探测系统测量了中子束斑的剖面,得到了该束线的初步实验测量结果.其中白光中子的全能谱测量范围eV—100 MeV,给出了不确定度分析;给出了中子注量率两个实验厅位置的满功率值;给出了白光中子在直径60 mm情况下的全能区束斑.通过与模拟结果的比较探讨了以上结果的合理性,并提出了改进计划.这些实验结果为以后该束线的核数据测量和探测器标定实验奠定了基础.     

非平衡辐射烧蚀对内爆中子产额的影响

 利用1维多群非平衡辐射输运RDMG程序，对不同能谱分布的辐射场驱动的靶丸的辐射烧蚀过程及中子产额进行了模拟计算，并与实验测量结果进行了初步比较。结果发现，辐射驱动源的能谱平衡性，特别是高能金M带成分对内爆靶丸产生预热效应，降低核燃料区压缩度，电子及离子温度，从而显著降低了中子产额。计算结果表明：中子产额随CH壳厚增加而下降，该变化规律与实验结果基本符合。     

D-T中子与平板型聚乙烯材料作用的次级中子角度谱实验研究

基于反冲质子法建立了一种测量D-T中子与平板型宏观样品作用的次级中子角度谱的实验方法.为保证探测器的能量线性并在较低的中子有效测量下阈(0.5 MeV)情况下获得好的中子-伽马射线甄别性能,采用高、低能段分别测量的方法.采用事件记录法,同时记录了次级中子和伴随伽马射线的脉冲形状甄别和脉冲幅度二维信息,利用基于ROOT数据分析平台编写的离线数据分析程序,完成了伴随伽马射线的挑选和扣除,以及高、低两能段反冲质子谱的拼接,并成功的将神经网络技术应用于中子能谱的解谱,获得了D-T中子与9和18 cm厚平板型聚乙烯材料作用的0.5-15 MeV的次级中子角度谱实验结果.实验模型的MC模拟由MCNP5完成,数据库采用ENDF-VI,实验结果和MC计算结果在实验不确定度范围内一致. 关键词： D-T中子 积分中子学 反冲质子法 次级中子能谱     

高能中子消失法的检验

以前在贫化铀／聚乙烯／铁组合球装置上进行的高能中子消失法的检验，存在的问题在于贫化铀内腔太小，距离的微小误差就会对实验结果产生很大影响，实验重复性差。因此用同样是中子增殖材料的铍代替贫化铀作补充实验。这样，一则可以减小因为距离的偏差对实验的影响；二则可能对^197Au(n，γ)、^198Au反应的影响再做研究。用铍／聚乙烯／铁组合球装置，在ns-200加速器上照射，用HPGe探测器测量．Au，Al，Nb高阈能指示剂的活化γ射线，确定它们在装置中的反应燃耗，以此检验高能中子消失法。     

电子与钠原子散射极化参数的计算

采用扭曲波方法对电子与钠原子非弹性散射截面，及与散射过程有关的极化参数进行了计算，将所得结果与实验值和CCC方法所得结果进行了比较.可以看出在中高能(5—10倍阈能)领域，扭曲波法是一种模型清晰、结果可靠的方法. 关键词：     

一种基于成像板的能量卡阈式快中子图像测量方法

为减小散射中子等较低能量的中子对快中子图像的贡献,提出了在成像板前依次紧贴金属卡阈片和富氢元素薄片的能量卡阈式快中子成像方法.该方法通过改变卡阈片材料、厚度等参数,可有效降低成像结构对某一能段中子的相对灵敏度.以14 MeV中子照相为例设计的能量卡阈式成像结构为TR成像板依次覆盖约150μm Pb膜和500μm聚乙烯膜,计算表明该结构对8 MeV以下快中子灵敏度小于其对14 MeV中子灵敏度的30%.利用K400加速器DT中子源开展了验证实验,结果表明能量卡阈式快中子成像结构能够有效消除样品散射中子引起的边界增强效应.     

亚千X光能谱仪响应曲线实验标定

介绍了在高强度带电粒子激发Ｘ射线光源装置上标定亚千Ｘ光能谱仪的总响应，给出了Ｘ射线二极管（铝阴极）的灵敏度的绝对标定值以及作为高能截止分光元件镍平面镜的反射率，并与国外理论值和实验值进行了比较。     

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。     

Neutronics studies of solid targets for spallation neutron source using Monte Carlo simulation

Neutronics studies for a solid target have been done with Monte Carlo high-energy particle transport code NMTC/JAM,when the proton beam with high kinetic energy bombards the target.The effect of the main parameters of the target on the neutron flux is discussed to optimize the target,which will be used for the concept design of the target of spallation neutron source.A target with its aspect ratio 1.5:1 or 2:1 gives the highest neutron flux.Tungsten is the most acceptable material from the technical and economical points of view.Beryllium as a moderating reflector can increase the neutron flux effectively.     

In-phantom neutron dose distribution for bladder cancer cases treated with high-energy photons

This work presents an estimation of the neutron dose distribution for common bladder cancer cases treated with high-energy photons of 15 MV therapy accelerators. Neutron doses were measured in an Alderson phantom, using TLD 700 and 600 thermoluminescence dosimeters, resembling bladder cancer cases treated with high-energy photons from 15 MV LINAC and having a treatment plan using the four-field pelvic box technique. Thermal neutron dose distribution in the target area and the surrounding tissue was estimated. The sensitivity of all detectors for both gamma and neutrons was estimated and used for correction of the TL reading. TLD detectors were irradiated with a Co⁶⁰ gamma standard source and thermal neutrons at the irradiation facility of the National Institute for Standards (NIS). The TL to dose conversion factor was estimated in terms of both Co⁶⁰ neutron equivalent dose and thermal neutron dose. The dose distribution of photo-neutrons throughout each target was estimated and presented in three-dimensional charts and isodose curves. The distribution was found to be non-isotropic through the target. It varied from a minimum of 0.23 mSv/h to a maximum of 2.07 mSv/h at 6 cm off-axis. The mean neutron dose equivalent was found to be 0.63 mSv/h, which agrees with other published literature. The estimated average neutron equivalent to the bladder per administered therapeutic dose was found to be 0.39 mSv Gy^?1, which is also in good agreement with published literature. As a consequence of a complete therapeutic treatment of 50 Gy high-energy photons at 15 MV, the total thermal neutron equivalent dose to the abdomen was found to be about 0.012 Sv.     

CCD相机对14MeV和2.5MeV中子瞬态响应特性

从理论上分析了中子在CCD相机拍摄图像中引起的瞬态干扰噪声的机理,并针对两种不同类型的CCD相机,在能量为14MeV和2.5MeV的低强度稳态中子源上开展了实验研究,分析了噪声特征与入射中子能量、入射角度、注量及CCD相机结构的关系。实验结果表明中子瞬态干扰噪声主要表现为脉冲噪声,且出现斑点现象,与理论分析结果相吻合。研究得出了噪声特征随入射中子注量变化的规律,比较了不同能量及不同入射角条件下的噪声特性,并分析了两种不同结构的CCD相机响应特性的差别。     

同步辐射标定平面镜反射率不确定度分析方法研究

为了提高多通道软X射线能谱仪的测量精度,2009年在北京同步辐射(BSRF)软X束线源上对多种材料的掠入射平面镜的反射率进行了标定.在标定实验的基础上,对光源的单色性、高次谐波以及源强稳定性、探测器响应一致性和数据采集统计误差等多项不确定因素进行了评估,给出了反射率的修正方法和相应的不确定度分析结果.     

Cosmic-ray neutron spectrometry by solid state detectors

Extensive data have been gathered since the early 1990s on the response of different detectors based on the registration of neutron-induced fission in bismuth, gold, tantalum by the spark replica counter and the thin film breakdown counter. These detectors make it possible to exploit the excellent characteristics of the fission reactions in bismuth, gold and tantalum for the measurements of high-energy neutrons.

Most of the investigations have been carried out at the quasi-monoenergetic neutron beam facility at The Svedberg Laboratory-TSL of the Uppsala University in cooperation with the Khlopin Radium Institute (KRI).

The responses of different fission detectors in the intermediate range of neutron energy (35–180 MeV) have been evaluated: a region where the predictive power of available nuclear reaction models and codes is not reliable yet. For neutron energy greater than 200 MeV, the fission-detector responses have been derived from the data of the proton fission cross-sections.

Finally, by using the ratio of the responses of these detectors, a simple and accurate way to evaluate the spectrum hardness can be obtained, thus providing a tool to obtain spectral information needed for neutron dosimetry without the need to know the entire spectrum.

The experimentally measured spectra obtained to-date have different shapes and they are also different from those calculated.

In this paper, a new approach will be reported to analyse the existing spectra by using response ratios of different detectors. Preliminary data have been already obtained for the high-energy neutron spectrum from the CERN concrete facility.     

Neutron production at the heavy ion research facility in Lanzhou

In this work, the neutron radiation field at Heavy Ion Research Facility in Lanzhou (HIRFL) was investigated. Total neutron yields, spectra and angular     

Radiative transfer in a scattering medium with angle-dependent reflective boundaries

Abstract

Radiative transfer in an anisotropically scattering slab with direction-dependent reflectivities at the interfaces is solved using the Pomraning–Eddington variational method. The interfaces are assumed to reflect specularly as a function of angle of incidence according to Fresnel's equation. The quantities of interest, such as the hemispherical reflectivity and transmissivity of the medium, are calculated for different optical thicknesses, single-scattering albedos and refractive indices of the medium. The results are compared with the exact numerical results and with those obtained using the average value of the reflectivities instead of the angle-dependent Fresnel reflectivity. Calculations are also performed for a semi-infinite medium and compared with results calculated using the average reflectivities.     

Comparative Study of Depth Dose Distribution of Fast Neutrons Using Solid State Nuclear Track Detectors

A comparative study was made for measuring neutron depth dose distribution in a water phantom by means of different solid state nuclear track detectors. The used detectors were Makrofol, CR-39 and LR-115 with threshold energies of 1 and 0.1 MeV, respectively. Two exposure positions were used, the source in contact with the surface and at 30 cm from the phantom surface. The fluence distribution of ²⁵²Cf as a function of distance in air and in the water phantom were investigated. It was found that the neutron build up factor depends on the irradiation geometry, its values were 1.7 and 1.4 for both exposure positions. These results are in good agreement with the calculated results given in literature. The neutron attenuation and relaxation length had been also determined.