基于分数阶自抗扰技术的核电站稳压器压力控制

针对传统PID在复杂的核电站稳压器控制系统中无法获得良好的控制效果的问题,提出了分数阶自抗扰控制器(FOADRC).该控制器将分数阶控制器与自抗扰控制器相结合,不仅具备分数阶控制器的快速与高精度特点,还具备自抗扰控制器的强鲁棒性和抗扰动性能,解决了ADRC技术中非线性状态误差反馈控制律调参较困难的问题.建立的稳压器压力控制的Simulink仿真模型表明,分数阶自抗扰控制器与传统PID控制和ADRC控制相比具有更加优良的性能指标.     

Computational analysis for prediction of pressure of PWR presurizer under transient conditions

A computer model has been developed for prediction of the pressure in the pressurizer under transient conditions.In the model three separate thermodynamic regions which are not required to be in thermal equilibrium have been considered.The mathematical model derived from the general conservation equations includes all of the important thermal-hydraulics phenomena occurring in the pressurizer,i.e.,stratification of the hot water and incoming cold water,bulk flashing and condensation ,wall condensation,and interfacial heat and mass transfer,etc.The bubble rising and rain-out models are developed to describe bulk flashing and condensation.respectively.To obtain the wall condensation rate,a one-dimensional heat conduction equation is solved by the pivoting method.The presented model will predict the pressure-time behavior of a PWR pressurzer during a variety of transients.The results obtained from the propesed mathematical model are in good agreement with available data on the CHASHMA nuclear power plant‘s pressurizer performance.     

用矢量差分法加工涡流增压器叶片及误差分析

阐述了用矢量差分法处理径、轴流式涡流增压器扭曲叶片的四维数控加工数学处理问题，并对其误差特性进行了分析，重点叙述了一种新型的曲面数学处理方式矢量差分法。利用该方法能有效、简便地对各种类型的增压器叶片凹凸模具曲面进行分析、计算和处理，从而大大简化了常规曲面造型涉及所需的大量数值处理工作     

基于混合遗传算法的稳压器优化设计

本文建立了电加热式稳压器容积及重量计算的数学模型,编制了相应的计算机程序,在此基础上,对稳压器容积及重量受一回路运行压力和反应堆冷却剂出口温度影响的敏感性进行了分析。在选取合理的优化变量及约束条件后,利用混合遗传算法对稳压器重量进行了优化设计,计算结果显示,与原方案相比,采用优化方案后稳压器重量减小了153%,优化效果显著。     

核电站稳压器水位控制系统数字化的实现及优化方案

根据模拟稳压器水位控制系统结构、功能以及运行原理的分析,展开对稳压器水位控制系统数字化的研究。在选择成熟商用单板机的基础上引入了数/模,模/数转换以及控制算法等实现了稳压器水位控制系统,并和稳压器水位仿真模型构成闭环运行,通过虚拟仪器监测此控制系统的运行情况,证实了本系统达到并超过了原有模拟控制系统的功能和性能。     

Thermal-hydraulic analysis on the effect of operator action in the loss of shutdown cooling system accident in a PWR

It is necessary to develop PSA methodology and integrated accident management technology during low power/shutdown operations. To develop this technology, thermal-hydraulic analysis is necessarily required to access the trend of plant process parameters and operator's grace time after initiation of the accident. In this study, the thermal-hydraulic behavior in the loss of shutdown cooling system accident during low power/shutdown operations at the Korean standard nuclear power plant was analyzed using the best-estimate thermal-hydraulic analysis code, MARS2.1. The effects of operator's action and initiation of accident mitigation system, such as safety injection and gravity feed on mitigation of the accident during shutdown operations are also analyzed.When steam generators are unavailable or vent paths with large cross-sectional area are open in the accident, the core damage occurs earlier than the cases of steam generators available or vent paths with small cross-sectional area. If an operator takes an action to mitigate the accident, the accident can be mitigated considerably. To mitigate the accident, high-pressure safety injection is more effective in POS4B and gravity feed is more effective in POS5. The results of this study can contribute to the plant safety improvement because those can provide the time for an operator to take an action to mitigate the accident by providing quantitative time of core damage. The results of this study can also provide information in developing operating procedure and accident management technology.     

核动力设备耦合优化设计研究

核动力设备重量是评价核动力装置性能的标准之一。蒸汽发生器与稳压器是反应堆一回路中的重要设备,在保证实现其各自功能的前提下,降低这2个设备的重量能提高整个核动力装置的性能。本工作基于秦山核电厂相关设备资料,自主开发了对蒸汽发生器和稳压器进行重量优化设计的计算程序,采用粒子群 模拟退火方法开展多参数优化设计。结果表明,通过参数的重新组合优化,2个设备重量之和减少了18.61%,优化效果显著,相关结果可作为工程设计参考。     

AP1000核电机组稳压器支撑加固的工程实践

AP1000核电机组稳压器通过底部4根垂直支撑进行支撑固定,三门核电l号机组稳压器垂直安装完成后,AP1000设计方美国西屋公司发布了设计变更,对稳压器支撑进行加固.文章主要介绍了三门核电1号机组稳压器垂直支撑设计变更的原因、设计变更现场实施的主要工序、现场施工的主要难点以及应对措施.     

比例喷雾阀的研制

介绍了核一级比例喷雾阀的性能参数、结构及其主要零件的材料。分析了比例喷雾阀冷态循环、流量特性、寿命试验以及地震、热态试验的试验过程及其技术要求。