公伯峡水电站高压电缆设计几个技术问题分析

结合公伯峡水电站电缆系统设计，对合理选择电缆截面、敷设方式及保护措施等技术问题加以介绍。由于目前电缆设计标准不太完善，因此设计中应结合电站具体情况，合理地选择和提出技术要求。     

锂离子电池健康状态估计方法

为研究动力锂离子电池的健康状态( state of health,SOH),根据SOH和荷电状态( state of charge,SOC)的定义以及电池的二阶电阻电容( resistance-capacitance,RC)等效电路模型,建立了基于恒流充电阶段电池电压曲线的SOH估计模型。通过分析电池循环寿命测试数据,利用恒流充电阶段电池电压曲线对SOH进行估计,并与试验数据进行了对比,在SOH值衰减至80%之前,SOH估计的相对误差均在±2%范围内,能较好地吻合试验结果。结果表明：所提出的估计方法具有可行性和精确性。     

基于迭代学习控制的混合误差轮廓控制

针对永磁直线同步电动机直接驱动XY平台系统中存在不确定扰动的问题,单轴上设计了基于干扰观测器的迭代学习控制器.迭代学习控制器可以抑制重复扰动,干扰观测器可以消除非重复扰动的影响,两者结合起来可增强系统对重复和非重复扰动的抑制能力.由于轮廓误差计算模型要求跟踪误差远小于期望轮廓曲率半径,所以设计了混合误差轮廓控制器,跟踪误差较大时只控制各轴位置,跟踪误差足够小时进行轮廓控制.仿真结果表明,该控制方法使直接驱动XY平台具有较强的鲁棒性和较高的轮廓精度.     

北美规范与中国规范关于冷弯薄壁型钢C形截面受压构件设计的比较

对比了北美规范CSA S136-07和中国规范GB 50018-2002中关于冷弯薄壁型钢C形截面轴压构件的名义轴压强度。首先介绍了北美规范和中国规范计算名义轴压强度的方法,然后针对控制构件名义轴压强度的2个主要参数,即屈曲应力和有效截面面积,对2本规范进行了深入对比,最后对典型C形墙架柱名义轴压强度进行了比较。研究结果表明：2本规范具有相同的屈曲应力,但依据2本规范计算的有效截面面积却不同;一般来说,根据GB 50018-2002计算的翼缘有效宽度远小于根据CSA S136-07计算的结果,然而依据CSA S136-07计算的腹板有效宽度则略小于依据GB 50018-2002计算的结果;2本规范名义轴压强度不同主要由C形截面翼缘和腹板有效宽厚比不同引起;当翼缘的宽厚比不小于17．8时,构件名义轴压强度的不同主要由翼缘有效宽厚比控制,根据GB 50018-2002计算的名义轴压强度小于根据CSA S136-07计算的结果;当翼缘的宽厚比小于17．8时,构件名义轴压强度的不同则主要受腹板有效宽度控制,依据GB 50018-2002计算的名义轴压强度略大于依据CSA S136-07计算的结果。     

基于深度学习的锂离子电池SOC和SOH联合估算

锂离子电池常被作为储能元件以实现电能的存储和转化,然而其荷电状态(state of charge,SOC)和健康状态(state of health,SOH)无法被直接测量。为了实现锂离子电池SOC和SOH联合估算,该文分析SOC和SOH之间的关联性,并提出一种基于深度学习的锂离子电池SOC和SOH联合估算方法。该方法能够基于门控循环单元循环神经网络(recurrent neural network with gated recurrent unit,GRU-RNN)和卷积神经网络(convolutional neural network,CNN),利用锂离子电池电压、电流、温度,实现锂离子电池全使用周期内SOC和SOH的同时估算,而且由于将锂离子电池的SOH估算值考虑到SOC估算中,能够消除锂离子电池老化因素对锂离子电池SOC估算造成的负面影响,从而提升SOC估算精度。两个锂离子电池测试数据集上的实验结果表明,提出的估算方法能够在不同温度和不同工况下实现锂离子电池全使用周期SOC和SOH联合估算,且获得较高的精度。     

双相不锈钢焊接接头疲劳强度

试验对SAF2205双相不锈钢纵向角接板焊接接头的疲劳强度进行了研究，用有限元计算热点应力集中系数，分别得出了名义应力和热点应力疲劳S-N曲线；用国际焊接学会推荐的方法进行统计处理，并和相同接头形式结构钢的疲劳强度进行了比较。试验表明，双相不锈钢纵向角接板焊接接头名义应力疲劳强度试验结果为FAT136，热点应力疲劳强度试验结果为FAT163，高于相同接头形式结构钢的疲劳级别；双相不锈钢的静载强度级别对其疲劳强度设计级别没有明显的影响。     

基于不确定T-S模型的模糊滑模自适应控制

提出一种不确定T-S模型的模糊滑模自适应控制方法。通过变换将该模型转换成3个组成部分：线性标称系统,已知非线性部分和未知不确定部分。针对它们设计3个控制器,其作用分别为：强迫系统沿着滑模面运动,消除已知扰动对线性标称系统的影响,克服不确定扰动(采用模糊滑模自适应控制,无需知道不确定的界限)。该方法无需求正定矩阵就能保证系统全局稳定。     

Modelling Calculi with Name Mobility using Graphs with Equivalences

In the theory of graph rewriting, the use of coalescing rules, i.e., of rules which besides deleting and generating graph items, can coalesce some parts of the graph, turns out to be quite useful for modelling purposes, but, at the same time, problematic for the development of a satisfactory partial order concurrent semantics for rewrites. Rewriting over graphs with equivalences, i.e., (typed hyper)-graphs equipped with an equivalence over nodes provides a technically convenient replacement of graph rewriting with coalescing rules, for which a truly concurrent semantics can be easily defined. The expressivity of such a formalism is tested in a setting where coalescing rules typically play a basic role: the encoding of calculi with name passing as graph rewriting systems. Specifically, we show how the (monadic fragment) of the solo calculus, one of the dialect of those calculi whose distinctive feature is name fusion, can be encoded as a rewriting system over graph with equivalences.     

钒微合金化低碳钢高温变形动态再结晶

利用热模拟压缩试验测定了不同钒含量的钒微合金化低碳钢在900～1000℃温度区间和0.1～1s-1变形速率范围内的真应力-真应变曲线.对曲线的分析表明:随钢中钒含量的增加,低碳钢的动态再结晶开始时间延长,变形奥氏体的动态再结晶名义激活能提高.实验钢薄膜试样的TEM观察表明,钢中的微量钒以固溶态存在于奥氏体中,微量的固溶钒对奥氏体动态再结晶起到抑制作用.     

Fracture experiments on through wall cracked elbows under in-plane bending moment: Test results and theoretical/numerical analyses

Fracture assessment of pipe bends or elbows with postulated through wall crack is very essential for leak-before-break qualification of primary heat transport system piping of nuclear power plants. The methodology for fracture assessment of cracked elbows is still in developing stage. Any new development in theoretical aspect requires experimental validation. However, fracture test data on cracked elbows is not so abundant as straight pipes. The earlier experiments on cracked elbows were focused mainly on the determination of limit load. Other fracture parameters e.g. crack growth, crack initiation load or crack opening displacement were not reported in the open literature. Against this backdrop, a comprehensive experimental and theoretical program on component integrity has been initiated at Reactor Safety Division (RSD) of Bhabha Atomic Research Center (BARC), India. Under this program, a number of fracture tests have been carried out on elbows with through wall circumferential/axial cracks subjected to in-plane closing/opening bending moment. These test data are then thoroughly analysed numerically through non-linear finite element analyses, analytically through limit load comparison and also through comparison of crack initiation loads by finite element and R6 methods. These test data may be utilized in future for validation of new theoretical developments in the integrity assessment of through wall cracked elbows.