56,54Fe(n, α)53,51Cr, 56,54Fe(n,p)56,54Mn反应截面计算及普适性模型参数优化研究

基于中子与Fe发生反应产生“氢泡”,及“氦泡”对新型核能利用系统壁材料的影响,开展了中子诱发56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn反应截面计算研究工作。本工作根据现有的56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn反应实验数据、评价数据,对TALYS程序调用的物理模型(包括能级密度、对修正、核温度、光学势参数等)进行参数调校,得到了一组普适性强的模型参数。基于调校的参数,本工作采用核反应程序TALYS理论计算56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn反应的截面、能量微分截面以及双微分截面,全部数据都能与实验数据、评价数据符合较好,且适用于较宽的中子能量区间0~175 MeV。本工作提出了56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn反应的普适性模型参数,促进了核反应理论的发展,为核数据的评价奠定了基础。     

Study of an unfolding algorithm for D-T neutron energy spectra measurement using a recoil proton method

A proton recoil method for measuring D-T neutron energy spectra using polyethylene film and a Si(Au) surface barrier detector is presented. An iteration algorithm for unfolding the recoil proton energy spectrum to the neutron energy spectrum is investigated. The response matrices R of the polyethylene film at angles of 0° and 45° were obtained by simulating the recoil proton energy spectra from mono-energetic neutrons using the MCNPX code. With an assumed D-T neutron spectrum, the recoil proton spectra from the polyethylene film at angles of 0° and 45° were also simulated using the MCNPX code. Based on the response matrices R and the simulated recoil proton spectra at 0° and 45°, the respective unfolded neutron spectra were obtained using the iteration algorithm, and compared with the assumed neutron spectrum. The results show that the iteration algorithm method can be applied to unfold the recoil proton energy spectrum to the neutron energy spectrum for D-T neutron energy spectra measurement using the recoil proton method.     

Micromegas中子探测器位置分辨特性的Monte-Carlo研究(英文)

利用GEANT4和Garfield气体探测器模拟程序模拟了Micromegas中子探测器位置特性。 在漂移极上加一层聚乙烯薄膜作为转换材料, 通过反冲质子法测量中子的位置。 提出了一套通过设定探测器上层结构的方案来得到探测器的位置分辨特性。 通过对模拟结果的分析与比较, 得到一种易于测定探测器位置分辨特性的方法。 该工作不仅可以优化气体探测器结构设计, 缩短实验周期, 而且还能极大程度地节约经费。 In the present work, the spatial resolution of Micromegas as a neutron detector was simulated with GEANT4 and Garfield program. The polyethylene foil was used as neutron converter. A new method based on structural setting on the top layer of the detector was adopted to obtain spatial resolution. According to our simulation, it turned out to be a better spatial resolution, and this method was easily realized in experiment.     

基于D-T紧凑型中子源的快中子照相准直屏蔽体设计及中子束特性模拟研究

中子照相是一种重要的无损检测技术,它能用于火工产品、毒品和核燃料元件等的检测。基于紧凑型D-T中子发生器,完成了一个用于快中子照相的准直屏蔽体系统（BSA）的物理设计。根据D-T中子源的能谱和角分布建立了中子源模型,采用MCNP4C蒙特卡罗程序,模拟了准直屏蔽体系统中中子和γ射线的输运,准直中子束相对于单位源中子的中子注量可以达到9.30×10-6 cm-2,准直中子束中主要是能量大于10 MeV的快中子;在设置的样品平面直径14 cm的照射视野范围,准直束中子注量的不均匀度为4.30%,准直束中中子注量与γ注量的比值为17.20,中子通量和中子注量比值J/Φ为0.992,说明准直中子束有好的平行性;准直屏蔽体外的泄露中子注量率与准直束中子注量率相比降低了2个量级。所设计的准直屏蔽体能满足快中子照相的要求。Neutron radiography is an important nondestructive testing technique. It can be used to detect the explosive devices, drug and the nuclear fuel element, etc. A beam-shaping-assembly (BSA) based on a compact D-T neutron generator is designed for fast neutron radiography in this paper. D-T neutron source model is constructed based on the neutron energy spectrum and angular distribution data. The transportation of neutron and γ-ray in the BSA is simulated using MCNP4C code. The neutron fluence of the collimated neutron beam with respect to the neutron source of the unit source is 9.30×10-6 cm-2. The collimated neutron beams is mainly fast neutrons with energies greater than 10 MeV. In the irradiation field range with a diameter of 14 cm, the neutron fluence uniformity of the collimated beam is 4.3%, the ratio of the neutron fluence to the gamma fluence in the collimated beam is 17.20, and the neutron flux and the neutron fluence ratio (J/Φ) is 0.992 which indicates that the collimated neutron beam has good parallelism. The leakage neutron fluence in outside of BSA is two orders of magnitude lower than that of the collimated neutron beam. The designed BSA can meet the need of fast neutron radiography.     

Calculation of the wide-angle neutron spectra from the ~9Be(d,xn) reaction in a thick beryllium target

The multi-layer computing model is developed to calculate wide-angle neutron spectra, in the range from0° to 180° with a 5° step, produced by bombarding a thick beryllium target with deuterons. The double-differential cross-sections(DDCSs) for the ~9 Be(d, xn) reaction are calculated using the TALYS-1.8 code. They are in agreement with the experimental data, and are much better than the PHITS-JQMD/GEM results at 15°, 30°, 45° and 60° neutron emission angles for deuteron energy of 10.0 MeV. In the TALYS-1.8 code, neutron contributions from direct reactions(break-up, stripping and knock-out reactions) are controlled by adjustable parameters, which describe the basic characteristics of typical direct reactions and control the relative intensity and the position of the ridgy hillock at the tail of DDCSs. It is found that the typical calculated wide-angle neutron spectra for different neutron emission angles and neutron angular distributions agree quite well with the experimental data for 13.5 MeV deuterons. The multi-layer computing model can reproduce the experimental data reasonably well by optimizing the adjustable parameters in the TALYS-1.8 code. Given the good agreement with the experimental data, the multi-layer computing model could provide better predictions of wide-angle neutron energy spectra, neutron angular distributions and neutron yields for the ~9 Be(d, xn) reaction neutron source.     

中子诱发232Th裂变初始碎片质量及动能分布Monte-Carlo研究

随着第四代反应堆以及先进核能利用系统的发展,对中子核数据提出了高精度、多核素、宽能区的新要求.目前,中国核数据评价库(CENDL库)中相关核裂变的数据较缺失,不足以满足当前核能发展的需求.因此,建立面向中子核数据需求的可靠计算方法和工具变得极为重要.本文基于Monte-Carlo方法建立了裂变碎片质量动能计算模型,研究了中低能中子诱发²³²Th(n,f)反应发射中子前裂变碎片的分布特性.对于裂变碎片质量分布,本模型计算结果与实验值最大偏差约1%,与GEF, TALYS程序计算结果 (与实验值最大偏差约2%)相比具有一定优势.对于发射中子前裂变碎片动能分布,本模型计算结果与实验数据一致.结果表明,所发展的计算模型能够较好地预测²³²Th(n,f)反应发射中子前裂变碎片数据,为中子诱发锕系核裂变反应计算提供一种新思路.     

基于紧凑型D-D中子发生器的热中子照相慢化准直器设计

热中子照相是一种重要的无损检测技术,是X射线照相技术的重要补充,小型化热中子照相系统有重要研究应用前景。基于紧凑型D-D中子发生器,采用蒙特卡罗程序MCNP-4C,通过中子和γ射线的输运模拟,完成了热中子照相慢化准直器的模拟研究与设计。慢化准直器准直比约为3.58,模拟研究结果显示,在D-D中子发生器中子产额大于5×10⁸ n/s条件下,样品平面内热中子注量率可大于10³ n/(cm²·s),准直中子束中热中子占比可大于74%,在Φ70 mm的照射视野范围内,热中子注量的不均匀度约为7.3%,基本满足热中子照相的成像要求。     

厚靶低中能9Be(d,xn)反应加速器中子源特性研究

利用PHITS程序评价计算了厚靶9Be(d, xn)反应加速器中子源的能谱和角分布数据，重点讨论了JQMD、INCL和INCL/DWBA三种核反应物理模型计算厚靶9Be(d, xn)反应中子辐射场分布的适用性。研究结果显示，基于INCL/DWBA耦合模型的PHITS程序计算所得到的厚靶9Be(d, xn)反应中子能谱和角分布数据能够较好地与实验数据符合，可以为厚靶9Be(d, xn)反应中子源特性研究及应用提供较为准确的中子辐射场数据。此外，设计了水冷大面积旋转铍靶的方案，并在5~25 MeV/5 mA入射氘能量下条件下，开展了靶面温度模拟研究，结果显示，靶面最高温度可控制在100 oC以下。     

Monte Carlo simulation of fast neutron-induced fission of ~(237)Np

The potential-driving model is used to describe the driving potential distribution and to calculate the preneutron emission mass distributions for different incident energies in the ~(237) Np(n, f)reaction. The potential-driving model is implemented in Geant4 and used to calculate the fission-fragment yield distributions, kinetic energy distributions, fission neutron spectrum and the total nubar for the ~(237) Np(n, f)reaction. Compared with the built-in G4 ParaFissionModel, the calculated results from the potential-driving model are in better agreement with the experimental data and evaluated data. Given the good agreement with the experimental data, the potential-driving model in Geant4 can describe well the neutron-induced fission of actinide nuclei, which is very important for the study of neutron transmutation physics and the design of a transmutation system.