Studying local liquid velocity in liquid–solid packed bed using the newly developed X-ray DIR technique

Combination of X-ray Digital Industrial Radiography (DIR) and Particle Tracking Velocimetry (PTV) techniques for local liquid velocity measurement (V_LL) has been newly developed and successfully applied for trickle bed reactor (TBR). The technique was validated against newly developed fiber optical probe technique. This work attempts to highlight the applicability of this newly developed technique on a liquid–solid packed bed reactor. In this work, liquid was represented by water and solids were represented by EPS beads. The EPS beads were chosen because of its low density property. Three superficial liquid velocities (V_SL) were applied to the system. The experiment was replicated four times. The digital industrial radiography (DIR) consists of a complementary metal oxide semiconductor (CMOS) digital detector and X-ray source. Results of this work suggest that the technique has been successfully applied and comparable with previous work that has been done in the literature. It also suggests that there will be a maximum measurable interstitial liquid velocity when it travel inside the packed bed. The measured V_LL can have a maximum range that is between 4 and 4.7 times that of its V_SL. For V_SL=0.42±±2%, the V_LL-Max is in between 1.7 cm/s and 1.9 cm/s, V_SL=0.84±±2%, the V_LL-Max is in between 3.6 cm/s and 4.0 cm/s, and for V_SL=1.11±±2%, the V_LL-Max is in between 4.3 cm/s and 4.8 cm/s.     

The magnetic structure of TbNiSiD1.78

TbNiSiD_1.78 has been studied by powder neutron diffraction below 100 K. The compound takes the hexagonal room temperature structure at 100 and 50 K (P6₃/mmc). At 2 K, below the antiferromagnetic ordering temperature of 10 K, there is a small orthorhombic distortion of the lattice. The refined unit-cell dimensions at 2 K (space group Pnma) are a=7.9505(2), b=4.02502(14), c=6.9823(2) Å. The magnetic moments of Tb are 8.71(6) μ_B, and are ordered antiferromagnetically along a.     

界面流法计算反应堆六角形燃料组件中子通量密度分布

利用界面流法计算两维六角形轻水堆燃料组件中子通量密度分布。子区内中子源在空间上采用二次分布近似，还考虑了六角形组件周边水隙对组件内中子通量密度的影响。根据提出的模型，编制了TPHEX－E程序，并对一些轻水堆六角形组件问题作了计算，计算结果与蒙特卡罗方法计算结果进行了比较，符合良好。本程序可用于六角形轻水堆燃料组件计算。     

中子寿命测井在评价管外窜槽中的应用

管外窜槽已成为制约中原油田注水开发的障碍，并造成了严重的经济损失。文中分析了管外窜槽的形成机理，重点介绍了注硼中子寿命测井技术用于管外窜槽监测的原理、工艺及解释方法。结合中原油田的应用实例，论证了中子寿命测井评价管外窜槽的有效性，为油藏动态监测提供了有效手段。     

中子辐照金刚石生成卡宾碳

金刚石在中子辐照下发生相转变,得到了线性结构的卡宾碳。所得产物为覆盖金刚石表面的黑色薄膜状物质,其拉曼光谱在2191cm-1处有强峰,归属于C≡C伸缩振动;同时,其俄歇电子谱的峰位与金刚石相比有5eV的位移,证实了卡宾碳的存在。在中子辐照条件下,金刚石向卡宾碳的转化可能是通过碳原子堆垛形式发生变化而实现的。     

The experimental determination of the neutron cross section for selected solvents

An experiment was conducted in order to determine the macroscopic neutron cross section of various solvents useful in neutron radiographic inspection. These solvents are used to dissolve the salts of high cross-section elements in order to formulate a fluid of maximal neutron cross section. The resulting fluid could then be used as a contrast enhancing agent in neutron radiographic inspection. This experiment was planned using statistical experimental design techniques. The results of this experiment provided a quantitative measure of the mean and standard deviation of the macroscopic neutron cross section for the nine fluids investigated. A control fluid was found to be in close agreement with published values.     

中子产额大于1.5×10^10n／s的密封中子管

报道了一种中子产额大于１．５×１０１０ｎ／ｓ、靶和离子源都可拆卸的密封中子管，以它为核心研制的密封中子发生器已被用于中子照像等领域，并取得了较好的结果。     

反散射数字辐射成像系统

反散射成像法是数字辐射成像的主要方法之一，介绍了获得反散射数字图像的实验装置，并着重分析了针对此装置获得的反散性图像的处理方法。     

扫描式数字X射线胸部摄影系统的研制

扫描式数字X射线摄影系统属DR范畴,除具有DR的一般优点外,还具有散射射线影响小(零本底)、低剂量和低成本三大优点.探讨了以固体线阵探测器为基础的扫描式数字X射线胸部摄影系统的构建,包括系统整体设计方案、关键技术问题的阐述以及系统性能分析,并提出了进一步提高系统性能的可行方法.     

铑自给能中子探测器的灵敏度

本文给出了铑自给能探测器的热中子灵敏度和中子灵敏度的理论计算公式、燃耗修正公式以及不同中子温度下的换算公式。运用这些公式对ZTRh 123型铑自给能探测器的热中子灵敏度和中子灵敏度进行了理论计算,并在反应堆中对其进行了实验验证。其结果表明,理论计算值和实验标定值是相吻合的。其偏差:热中子灵敏度为8.5％,中子灵敏度为3.9％。