热电联产压水堆核电机组解耦控制  

Decoupling control of cogeneration PWR nuclear power plant

作　　者：张茹 孙培伟[1] 魏新宇[1] ZHANG Ru;SUN Peiwei;WEI Xinyu(School of Nuclear Science and Technology,Xi′an Jiaotong University,Xi′an 710049,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049

出　　处：《哈尔滨工程大学学报》2023年第12期2201-2207,共7页Journal of Harbin Engineering University

基　　金：国家自然科学基金项目(11875218).

摘　　要：为了在运核电站进行热电联产改造时,保证原有系统和供热系统之间的协调稳定控制,本文针对某压水堆核电机组热电联产改造后的解耦控制进行研究。采用主蒸汽抽汽的方案搭建对象模型,通过辨识方法得到各子系统传递函数。利用相对增益矩阵方法进行各子系统间的耦合性分析,采用单位阵解耦法设计解耦器,并基于Matlab/Simulink仿真平台进行验证。结果表明:设计的解耦控制器对热电联产改造后的系统可以取得较好的解耦效果,实现了一回路系统、二回路系统和供热系统的协调稳定控制。本文对其他类型核电机组热电联产后协调稳定控制系统的设计具有参考价值。To ensure the coordination and stability control among the primary circuit system,the secondary circuit system and the thermal energy supply system in the cogeneration reform of the operating nuclear power plant(NPP),this study investigated the decoupling control after the cogeneration reform of a pressurized water reactor(PWR)NPP.First,the object model of cogeneration PWR was developed to extract steam from the main steam pipe.The transfer functions of subsystems were obtained using the identification method.Then,the relative gain array method was used to analyze the coupling among subsystems of the model.Finally,the decoupling controller was designed using the unit matrix decoupling method,which was verified on the Matlab/Simulink simulation plat-form.The results show that the designed decoupling controller achieves a good decoupling effect for the systems af-ter the cogeneration reform.It also realizes the coordinated and stable control of the primary circuit,secondary cir-cuit,and thermal energy supply systems.Moreover,this study provides a reference for the design of coordination and stability control systems of other types of NPP after cogeneration reform.

关 键 词：压水堆核电机组 热电联产 解耦控制 相对增益矩阵 耦合性分析 单位阵解耦 解耦控制器 协调稳定控制 

分 类 号：TL361[核科学技术—核技术及应用]