石墨双晶单色器性能检验及应用

中子能量选择成像作为一种前沿中子成像技术,可实现传统白光中子照相技术无法实现的功能,如研究工程材料中的晶粒分布、应变/应力分布、织构测量和相变分析等。本文依托中国先进研究堆(CARR)上的中子成像测试平台,在国内首次研制了石墨双晶单色器,建立能量选择中子成像技术。飞行时间实验测试结果表明,该双晶石墨单色器在选择4×10^-10 m的中子时波长分辨率可达2.6%,优于3.0%的设计指标。虽然在冷源未开启的实验条件下该石墨双晶单色器产生了较多的次级中子,但基于现有条件开展的镍基高温合金的中子能量选择成像实验能清楚分辨特定取向微晶粒的形貌及分布。结果表明研制的石墨双晶单色器可在CARR上开展能量选择成像实验,随着未来CARR冷源的开启,次级中子数量降低,中子束流品质进一步提高,将开展高质量的中子能量选择成像实验。     

双能量X射线荧光全息图重构算法消除孪生像的模拟研究

X射线荧光全息术以样品内部的发光原子作为相干光源进行全息成像,可以直接观测到晶体内部原子的三维排列结构.和传统的全息术一样,X射线荧光全息术也遇到了孪生像问题.本文以27个Fe原子成立方排列的结构为模型,采用双能量荧光全息图重构算法研究入射X射线能量的选取对消除孪生像效果的影响.结果表明:记录荧光全息图的两个X射线能量越接近(对于内探测器全息术而言,最小能量差取决于单色器和探测器的能量分辨率;对于内源全息术而言,最小的能量差取决于元素的两个紧邻荧光能量差和探测器的能量分辨率),消除孪生像的效果越好;而入射X射线的能量越高,则原子像的分辨率越高.     

CARR堆HRPD谱仪垂直聚焦单色器的选取和强度增益计算

垂直聚焦单色器技术是提高样品位置中子强度的有效手段。本文应用蒙特卡罗模拟方法对中国先进研究堆（CARR）旁高分辨中子粉末衍射仪（HRPD）的垂直聚焦单色器进行了优化选取，得到了垂直聚焦单色器高度，聚焦曲率半径和倾角等参数值，计算了使用垂直聚焦单色器相对于平板单色器的强度增益和样品处聚焦束尺寸。     

中子单色器姿态调整台

中子单色器姿态调整台是大多单色中子散射谱仪所必需的机械部件之一,主要用来安放晶体单色器,并可通过远程控制对单色器进行姿态调整以保证得到所需的单色中子。该装置体积小、自由度多、运动精度高,是一集光机电和计算机控制技术为一体的五自由度运动设备。该装置研制成功后将首先应用于中国先进研究堆中子残余应力谱仪上。     

正八面体含氢晶格中子内源全息成像的初步模拟研究

中子全息成像是利用一定波长的单能热中子对样品微观三维结构进行成像的检测技术。本文简要介绍了中子全息成像技术的原理和应用,并用数值方法对正八面体含氢晶格的中子全息成像和重建过程进行模拟,同时分析统计噪声、探测波长等关键实验参数对成像结果造成的影响,获得了与实际相符的结果。文中所用模拟方法及其结论可被用于进一步理论和实验工作的开展。     

中子应力谱仪双聚焦Si单色器设计、模拟与测试

本文对中国先进研究堆中子应力谱仪使用的双聚焦Si单色器进行了设计、模拟和测试。采用SIMRES模拟程序确定了单色器垂直曲率及Si片厚度的最优值,并得到品质因数与散射角、单色器水平曲率和波长的依赖关系。实际测试结果表明,与平板Cu单色器相比,使用双聚焦Si单色器样品处中子强度提高了15倍。     

中子应力谱仪常用聚焦单色器的模拟与比较

用蒙特卡罗中子射线追踪程序McStas对中子衍射应力谱仪单色器部件进行模拟优化:以Cu(220)比较了单色器起飞角和准直系统对样品处中子注量率、分辨率的影响;计算得到给定条件下单色器最佳单晶条数和镶嵌度;单晶条倾角精度建议好于0.1°;计算了Cu(222)、(220)和(002)在不同起飞角情况下获得的中子注量率;相同条件下,Cu和Ge常用晶体单色器中以Cu(220)获得的中子注量率最大,而Cu(222)获得的波长分辨率最佳。     

锗单晶真空热压形变设备和工艺

中子单色器是中子散射谱仪的关键部件之一。使用效率更高的新型中子单色器将给中子散射谱仪带来极大的性能提升，垂直聚焦中子单色器可提高样品位置处中子束强度2～5倍，相应的中子散射实验测量时间将缩短2～5倍。显然，垂直聚焦中子单色器在提高反应堆中子源的利用效率上是一种经济有效的手段。考虑到新旧谱仪对于中子单色器的迫切需求，我们决定建立一个自主研发聚焦中子单色器工艺平台。     

中子单色器五轴姿态调整台的研发

单色器台是用来放置中子散射谱仪重要部件——中子单色器的装置。在中子散射实验中，单色器可起到把从反应堆引出的白光中子束单色化的作用。中子残余应力谱仪设计使用2个单色器：双聚焦Si单色器和平板Cu（220）单色器。     

CARR中子残余应力谱仪的设计与应用

中国先进研究堆(CARR)旁的中子残余应力谱仪是我国第1台利用中子衍射方法测量残余应力的设备。它的样品台及部分附属设备从瑞典引进,结合CARR的实际情况,完成了概念设计、物理设计及机械加工,目前谱仪正在调试中。新的单色器屏蔽体起飞角在41°～109°连续可变,采用五维姿态调整台,方便灵活地调整单色器的位置。使用双聚焦Si(311)单色器,谱仪的分辨可以达到0.2%。一维中子位置灵敏探测器ORDELA1128N的主要指标与REST上使用的ORDELA1150N的相比有了很大改进。谱仪的附属设备多样,具备开展织构测量和材料原位拉伸等实验研究的能力。     

Characteristics of Neutron Guide Tubes in Upgraded JRR-3

Abstract

The JRR-3 has been upgraded to be a new high performance research reactor JRR-3M with neutron guide tubes on a large scale and a cold neutron source. The neutron fluxes and spectra were measured at the end of the two thermal and three cold neutron guide tubes. The gain of the cold neutron source is also found from these spectra. The neutron fluxes of thermal neutron guide tubes with characteristic wavelength 2 Å are 1.2x10⁸ n/cm².s at a reactor power of 20 MW. The neutron fluxes of cold guide tubes are 2.0x 10⁸ n/cm².s with characteristic wavelength 4 Å and 1.4x10⁸ n/cm².s with 6 A when the cold neutron source is operated. The neutron spectra measured by the time-of-flight method agree well with their designed ones. The gains of the cold neutron source are 8 for 4 Å and 20 for 6 Å at a reactor power of 20 MW.     

冷中子三轴谱仪的整体配置和主要部件的参数设计

从冷中子导管系统的实际情况出发,以程序模拟为主要手段,通过计算和分析得到最重要的设计参数：可用中子波长范围、样品处束流强度和能量分辨率。在这些参数的基础上,结合实际给出了谱仪的整体配置以及主要部件的部分参数,如能量和动量转移范围、单色器和分析器的起飞角范围和嵌镶角、样品台散射角、准直器的准直度及本底和剂量要求等。     

反应堆上应力测量谱仪的优化设计

主要是针对稳态堆上专门做应力测量的两轴谱仪优化设计的研究。首先介绍了研究布拉格峰的宽度和强度的公式;讨论了两种不同情况下-放置在中子导管上和束导管上的应力谱仪,对于给定的分辨率,如何选择准直器的发散度和单色器的镶嵌角。     

Some Studies on the Time Resolved Energy Spectrum Reconstruction for Pulsed Neutron Source

The purpose of this article is to present some new numerical results concerning the time resolved energy spectrum reconstruction of a short pulsed neutron source, like one created in plasma focus devices. An MCNP code is used to simulate a time dependent neutron source, plastic scintillator detectors, and their recorded signals. A Monte Carlo program reconstructs spectrum using the signals produced by MCNP code. By the numerical computations we determined the optimum number of four detectors which are needed to be placed at 0, 10, 18 and 30 m from the source, respectively. A time resolution about 12 ns and an energy resolution of 40 keV are obtained. Neutron scattering in the air is considered, and it is found that the intensity of spectrum is increased by 6%.     

Development of Wide Band Neutron Monochromator Consisting of a Stack of Multilayers

A wide band neutron monochromator consisting of a stack of four multilayers on two Si wafers has been developed. One multilayer has 201 Ni/Ti layers. The layer thickness is gradually changed in order to extend the neutron reflection wavelength range similar to a supermirror. Multilayers were fabricated by the vacuum evaporation methods on each side of a Si substrate of 225 μm in thickness. Neutron reflectivity was measured by the θ-2θ reflectometer using cold neutrons. The neutron reflection wavelength was broadened to 19–40 nm by this stack from 26–40 nm of one multilayer.     

Efficient fission neutron spectrum matrix representation by singular value decomposition technique

In order to treat efficiently a huge fission neutron spectrum (FNS) matrix in a criticality calculation, the singular value decomposition (SVD) technique is introduced to an FNS matrix representation. The required number of SVD components for reconstruction of an FNS matrix is expected to be small since an incident neutron energy dependence of FNS is not so significant. The proposed technique of an SVD-based representation for a fission source term is tested in several fast critical systems. Through an observation of critical eigenvalue dependence on the number of considered SVD components, only six or seven components are required to obtain a critical eigenvalue which agrees with the reference solution within 10^?4 dk/kk′. It is also confirmed that a small reactivity effect caused by neutron spectrum shifting can be accurately calculated with the proposed technique.     

Television Imaging System for Fast Neutron Radiography Using Baby Cyclotron

Abstract

A television imaging system for fast neutron radiography (FNR-TV) developed using the fast neutron source reactor YAYOI was applied to the baby-cyclotron based fast neutron source to get images of thick objects quickly. In the system the same technique as a current television imaging system of thermal neutron radiography was applied, while the luminescent converter was used to detect fast neutrons.

Using the CR39 track etch method it took about 7 h to get an image, while the FNR-TV only 20 s enough for taking the same object. However the FNR-TV imaging result of the simulation model of a large explosive device for the space launch vehicle of H-2 type was not so good as the image taken with the CR39 track etch method. The reason was that the luminescence intensity of the FNR-TV converter was a quarter of that in the YAYOI.     

AB-BNCT中子靶物理设计分析

质子加速器适用于为硼中子俘获治疗提供中子源，其中子源强及能谱较反应堆中子源更具可调性。中子靶物理计算分析是加速器中子源设计的基础，为其提供粒子能量、流强等参数需求分析，并为靶体结构尺寸设计、中子慢化和屏蔽分析等提供前端参数。本文利用MCNPX蒙特卡罗程序，通过对质子打靶的中子产额和能谱、靶体能量沉积、打靶后靶材放射性活度和中子出射空间角分布等进行研究，提出能量2.5 MeV质子轰击100～200 μm锂靶的设计，并用模拟计算数据论证其合理性。该设计中子源在1 mA流强质子轰击下，源强可达9.74×10¹¹ s^-1；拟设计15 mA、2.5 MeV质子束产生的中子源，在治疗过程中靶材放射性活度累积最大值约为1.44×10¹³ Bq。