一种计算碳/碳复合材料浸渍量的理论公式

在研究碳／碳(C/C)复合材料的浸渍碳化(IC)工艺的改进技术中，对各种影响因素进行了综合分析，提出了一种计算C/C复合材料浸渍量的理论公式，这对正确估计C/C复合材料的IC效果、研究IC工艺与C/C复合材料宏观性能之间的关系具有一定的指导意义。     

智能家居环境监测控制系统的设计

介绍了一种以单片机AT89C52为核心的智能家居环境监测控制系统,实现温度、相对湿度以及光照强度等级等进行检测,并进行自动控制,以提高环境的舒适度.该系统性能可靠,结构简单,能实现对环境参数的自动调节.     

嵌入式电镦机控制系统设计

针对传统电镦机控制系统的存在问题,设计以S3C44B0X微处理器及μC/OS-Ⅱ嵌入式操作系统为平台的新型电热镦粗控制系统,完成了数据采集、过程控制以及人机交互等任务.本系统与传统的电热镦粗控制系统相比,具有自动化程度高、控制精度高、操作人性化及文件管理等优势.     

LiNi0.6Co0.2Mn0.2O2@LiMn0.6Fe0.4PO4/C复合正极材料的制备及性能

采用简单的机械球磨混合法制得NCM@LMFP/C(LiNi_0.6Co_0.2Mn_0.2O₂@LiMn_0.6Fe_0.4PO₄/C)复合正极材料,系统地研究了NCM与LMFP/C复合比例(9∶1,8∶2,7∶3,6∶4,5∶5)对材料电化学性能和热稳定性的影响.使用X射线衍射仪(XRD)、扫描电子显微镜(SEM)和差示扫描量热仪(DSC)对复合正极材料的结构与形貌进行表征研究.研究结果表明:当NCM与LMFP/C复合比例小于8∶2时,亚微米级LMFP/C出现富集、团聚,将NCM包埋其中.当NCM与LMFP/C复合比例为8∶2时,LMFP/C均匀地包覆在NCM颗粒表面或填充于其颗粒空隙中,材料的电化学性能最优、热稳定性良好:电流为0.1 C和1 C时的放电比容量分别为180.1和165.0 mAh/g,均高于理论测算容量(178.9和164.3 mAh/g);循环80周后容量保持率为95.7%,优于NCM(94.9%);复合正极材料热失控温度...     

Phase and microstructure of tungsten coating on C/C composite prepared by double-glow plasma

W-coated C/C composite is the most interesting as the ITER plasma facing components. In this paper, a dense W-modified layer was prepared on the C/C composite substrate by double-glow plasma method using pure W as target. Argon was input into the chamber as the plasma and the reactive gas. Phase and microstructure of as-prepared coating were examined by the X-ray diffraction and scanning electron microscopy, respectively. The results indicated that the dense W-modified layer could be successfully coated on the surface of the C/C composite substrate by double-glow plasma method. The W-modified layer was made of many columnar grains extending perpendicularly outward from the C/C composite substrate. There was a transition layer honeycomb-like between W coating and the C/C composite substrate. The adhesive force of the W coating and C/C substrate was about 21 N.     

原始成分组成对Ti(C,N)基金属陶瓷烧结性能的影响

采用真空烧结工艺制备了Ti(C,N)基金属陶瓷,研究了原始成分组成对材料烧结特性和力学性能的影响规律。结果表明:保持Mo/(Mo+Ni)为定值,随着硬质相成分的增加,烧结体抗弯强度降低,硬度增加;硬质相成分TiN含量超过一定阈值时,烧结体疏松导致硬度和抗弯强度同时大幅下降;TiN含量保持定值,硬质相成分含量增加,烧结体硬度增加,抗弯强度下降;粘结相成分用Co部分替代Ni,随Co含量的增加,烧结体硬度略有升高的基础上抗弯强度升高。     

C_(60)衍生物的放射性碘标记

富勒烯Ｃ6 0 是由 60个碳原子组成的球型分子 ,包含 1 2个五元环和 2 0个六元环 ,直径为0 .71ｎｍ。独特的结构赋予了它特殊的物理、化学和生物性质。Ｃ6 0 是一个优良的电子接受体 ,通过光诱导产生单重态氧的效率高达 1 0 0 % ,被喻为“单重态氧的发生器”。它极易与游离基反应 ,又被喻为“吸收游离基的海绵”。它具有 3 0个双键 ,可以发生许多有机反应 ,连接各种化学药物 ,是药物设计的理想载体[1] 。Ｃ6 0 仅溶于一些非极性和弱极性的有机溶剂 ,在水等极性溶剂中不溶。富勒烯作为药物载体 ,首先要制成水溶性衍生物。更为重要的是还必须了…     

Aspen 软件在低温精馏分离稳定同位素13C中的应用

本工作对低温精馏分离¹³C同位素的稳态模拟与动态模拟进行了研究。使用商用流程模拟软件Aspen Plus建立低温精馏过程的稳态模型,通过对比模拟数据与实验数据,验证物性参数和模型的可靠性。使用Aspen Dynamics建立低温精馏过程的动态模型,动态模拟结果与实验数据吻合良好。结果表明,可以使用Aspen Dynamics对碳同位素分离过程进行动态特性研究,并对精馏过程进行开车时间预测、控制方案分析、操作性分析和安全性分析等。     

Calculation of fuel burnup and radionuclide inventory in the Syrian miniature neutron source reactor using the GETERA code

Calculations of the fuel burnup and radionuclide inventory in the Syrian miniature neutron source reactor (MNSR) after 10 years (the reactor core expected life) of the reactor operation time are presented in this paper using the GETERA code. The code is used to calculate the fuel group constants and the infinite multiplication factor versus the reactor operating time for 10, 20, and 30 kW operating power levels. The amounts of uranium burntup and plutonium produced in the reactor core, the concentrations and radionuclides of the most important fission products and actinide radionuclides accumulated in the reactor core, and the total radioactivity of the reactor core were calculated using the GETERA code as well. It is found that the GETERA code is better than the WIMSD4 code for the fuel burnup calculation in the MNSR reactor since it is newer, has a bigger library of isotopes, and is more accurate.     

A ctivation measurement of neutron distribution in intermediate energy heavy ion target area

The distribution of neutrons produced by the reaction of 50MeV/u ^12C-ion on a thick Cu target are studied.The neutrons are measured with threshold activation detectors.Al.F,C,Al and In activation samples were used to measure neutrons with energy greater than 7,11,20,50MeV and thermal neutrons,respectively,The fluence rate,energy and angular distributions of neutrons,total neutron yield of 12C-ion and the emission rate in the forward direction of neutrons over 11 and 20MeV were obtained.