导电聚合物基电致变色器件的研究进展

导电聚合物作为电致变色活性材料是目前最有应用前景的智能材料之一。本文概述了电致变色器件的基本结构和导电聚合物的电致变色机理,着重介绍了多种导电聚合物基电致变色器件的特点、组成及制备,并展望了未来电致变色器件的发展及应用趋势。     

聚(3,4-乙撑二氧噻吩)导电织物的制备、结构及其电致变色性能

本文采用原位聚合法, 以耐酸性好的涤纶为基底, 制得了聚(3,4-乙撑二氧噻吩)/涤纶复合导电织物[Poly(3,4-ethylenedioxythiophene)/conducting terylene textile, PEDOT/CTT], 分析了该导电织物的形貌、导电性能及结构, 并对其电致变色性能进行了初步测试. 实验结果表明, 所得到的PEDOT/CTT具有良好的导电性和一定的电致变色性能, 有望在全固态电致变色织物的制备中获得应用.     

水轮发电机哈密顿建模中参数的仿真分析

将水轮发电机控制器(自动电压调节器AVR和电力系统稳定器PSS)用电路等效,获得控制器的哈密顿函数,从而方便于建立包含水轮发电机和控制器的整体对象系统哈密顿模型.本文通过对以上整体对象系统的仿真分析,验证了控制器等效电路对低频振荡抑制作用的有效性,给出控制器等效电路中参数配合和取值范围与低频振荡的关系,为进一步研究水轮发电机组的机电联合控制提供基础.     

聚己内酯/纳米二氧化硅复合体系环带球晶形貌及结晶行为研究

采用溶液浇铸的方法制备了聚己内酯(PCL)/疏水性纳米二氧化硅(R974)复合体系薄膜,利用偏光显微镜、差示扫描量热仪、扫描电镜等研究了R974对PCL环带球晶形貌及结晶行为的影响,并从微观层次探讨了PCL/R974环带球晶可能的形成机理。结果表明,PCL/R974环带球晶是由扭转生长的片晶构成。R974的加入可诱导PCL环带球晶的形成,拓宽环带球晶形成温度。R974含量越高,PCL形成环带温度越低,环带周期越小,环带结构越规整。等温结晶时,R974加入并未改变PCL异相成核机理,但会影响其结晶动力学。当R974含量≤4%(wt)时,其异相成核作用占主导,促进了PCL结晶过程;当R974含量4%(wt)时,其对于球晶生长的阻碍大于异相成核作用,最终抑制了PCL的结晶。     

光源近场测量在LED光学设计中的应用与研究

在LED光学设计中,传统方法多以LED光源的远场测试数据为设计依据,而远场测试仅仅是对LED光源相对粗糙的测量,并不能精确地描述光源的空间光分布情况。对LED光源详细空间光分布信息的获取,即LED光线集的获取已经成为LED光学设计的瓶颈问题。获取并合理利用精确、详实的LED光源信息尤其是光源空间光分布信息是LED光学设计的关键点。分别利用单颗LED芯片和LED模块做了两组对照实验,并利用照明解析软件对获得的实验数据进行处理和分析,通过对比实验中光源远场测试和近场测试获得结果之间的差异,强调了通过LED光源近场测试获取光源光线集对LED光学设计的重要作用。实验结果表明,LED光源近场测量获取的光源光线集可以为LED光学设计提供更为详细的光源的光空间分布信息。     

水力机组紧急停机过程轴系振动仿真分析

水力机组因事故进入紧急停机过程时,机组转速急剧上升然后逐渐减速,轴系振动幅度产生较大变化,可能诱发轴系破坏.论文基于已建立的水力机组轴系暂态计算模型,构建完整的水力机组仿真系统,研究在机组紧急停机暂态过程中,机组角速度的变化与轴承刚度、轴系阻尼系数之间的关系,以及轴系参数对发电机转子和水轮机转轮振动幅度的影响.仿真表明,发电机转子和水轮机转轮振动幅度与机组转速变化趋势一致,在最大转速时振幅达到最大,建议将该点作为安全校核点.     

n+233U裂变碎片质量分布的唯象模型研究

本模型基于裂变多通道无规颈断裂模型,考虑宏观液滴能、壳效应能以及壳效应与温度的关系,得到参数化的势能表示形式。通过拟合不同测量方法得到的实验数据(经过评价) 获得3 组模型参数。3 组参数计算的碎片质量分布均很好地再现了不同能点的实验数据,除了基于动能法实验数据得到的参数外,其14 MeV的计算结果与实验数据符合较差。研究发现,不同入射中子能量的裂变碎片质量分布有4 个主要交叉点,在叉点之上的产额随入射中子能量增加减少,之下的产额则随入射中子能量上升;内侧(或外侧) 的两个交叉点质量数之和近似等于裂变复合核的质量数;不同裂变系统的重峰左侧的交叉点都保持在132 附近。Present model was based upon Brosa model, where macro energy,shell effect energy and its decreasing with system temperature were considered and parameterized. 3 sets of model parameters were obtained by fitting to 3 groups of evaluated experimental data, respectively, where the groups were classified by measured method: radiochemistry (RA) method, double kinetic energy (KE) method, and both (ALL). All the 3 sets of parameters could well reproduce themeasured mass distributions on different energies, except the KE set on 14 MeV. The result shows the mass distributions mainly had 4 trend turning points, above which the yield decreasing and below which the yield increasing with energy.The sum of the 1st and 4th (or 2nd and 3rd) point positions was equal to the compound nuclei mass approximately. And the 3rd point was kept at ~132 constantly for different fission systems n+233 U, n+235U, n+233Pu.     

232Th 中子诱发裂变产额数据比对评价

232Th 中子诱发裂变产额在Th/U 燃料循环的核能开发中具有重要的意义,在现有国际评价产额数据库基础上,结合最新的实验数据,对产物核的质量分布和反应堆计算所需的重点产物核进行了比对。这些产物核包括95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd 和153Eu 等,对有分歧的133Cs,152Sm 和153Eu 累积产额数据进行了评价调整。最后推荐给出了n+232Th 裂变的产额数据库,作为CENDL 库的组成部分。The yields of n+232Th fission are important in study of the Th/U fuel cycle. Based upon the evaluated nuclear data libraries and recent experimental data,comparison and evaluation for yield mass distribution and cumulativeyield were performed for those products are needed and important in reactor calculations,including 95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd adn 153Eu etc. Adjustments were made for 133Cs, 152Sm and 153En which have discrepancies among the libraries. Database for n+233Th fission yield is recommended as a part of CENDL update.     

Calculation of prompt fission neutron spectra for 235U(n,f)

The prompt fission neutron spectra for the neutron-induced fission of ²³⁵U at E_n < 5 MeV are calculated using nuclear evaporation theory with a semi-empirical model, in which the nonconstant and constant temperatures related to the Fermi gas model are taken into account. The calculated prompt fission neutron spectra reproduce the experimental data well. For the n(thermal)+²³⁵U reaction, the average nuclear temperature of the fission fragment, and the probability distribution of the nuclear temperature, are discussed and compared with the Los Alamos model. The energy carried away by γ rays emitted from each fragment is also obtained and the results are in good agreement with the existing experimental data.     

20MeV以下快中子与56Fe非弹性散射截面的分歧研究

56Fe的非弹性散射截面在核装置中子输运计算中扮演着重要的角色,但无论从实验数据还是从评价数据,非弹性散射截面都存在很大分歧,它的数据直接影响到核装置的设计、建造与运行维护。本工作从实验数据本身出发,深入分析了不同实验室测得的847 keV的γ产生截面的分歧,经转化后补充非弹性散射截面的实验空白能区,并同时利用满足全截面、去弹截面等截面自洽关系的评价方法推荐了高精度的快中子与56Fe的非弹反应截面结果。积分检验表明,新的非弹截面的改进使得评价数据与积分实验结果一致,较CENDL-3.1的评价数据结果有显著改善。Knowledge about the inelastic scattering cross section of 56Fe is very important in neutron transportation calculation. However there are great discrepancies not only between experimental data but also between evaluated data. More detail analysis was performed for inelastic scattering cross section in the fast range up to 20 MeV where there are significant differences among the main evaluated libraries, mainly caused by the different inelastic scattering cross section measurements. The large discrepancies on 56Fe(n, n₁'γ) cross section which could fill the neutron energy blank of the 56Fe(n,inl) were clarified and were converted to the inelastic scattering cross section of 56Fe. And the high-quality results were evaluated by using the unitarity constrain among total cross section, noelastic reaction and other reactions. The integral experiment result indicates that the new evaluated result of inelastic cross section brings greater improvement than that of CENDL-3.1.