首页 | 本学科首页   官方微博 | 高级检索  
     

基于SPSA的蒸汽发生器液位MPC系统性能优化方法研究
引用本文:耿鹏程,史长青,孔祥松,刘航,刘佳彬,江绍波.基于SPSA的蒸汽发生器液位MPC系统性能优化方法研究[J].核动力工程,2022,43(5):168-175.
作者姓名:耿鹏程  史长青  孔祥松  刘航  刘佳彬  江绍波
作者单位:1.中广核工程有限公司核电安全监控技术与装备国家重点实验室,广东深圳,518172
摘    要:核电厂蒸汽发生器(SG)液位变化过程具有强非线性且存在“虚假水位”现象,传统SG液位控制系统多采用固定参数比例-积分-微分(PID)控制器,但传统PID控制方法不具备自优化、自适应、自学习等能力,使得控制系统性能难以达到并保持最佳。为提高机组瞬态响应能力以及核电厂的稳定性、安全性和经济性,提出了一种基于并行摄动随机逼近(SPSA)算法的模型预测控制(MPC)方法。该方法采用MPC系统代替传统PID控制系统,并利用SPSA实现液位控制系统参数的整定优化,从而实现SG液位控制系统的性能优化。通过仿真试验验证了本方法能够有效提高SG液位控制参数的整定效率以及控制系统稳定性。 

关 键 词:蒸汽发生器(SG)    模型预测控制    控制系统性能优化    并行摄动随机逼近算法
收稿时间:2021-09-26

SPSA-based Performance Optimization Method for Steam Generator MPC System
Affiliation:1.State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd., Shenzhen, Guangdong, 518172, China2.Xiamen University of Technology, Xiamen, Fujian, 361021, China
Abstract:The level change process of steam generator (SG) in nuclear power plant has strong nonlinearity and the phenomenon of "false water level" exists. Traditional SG level control systems mostly use fixed-parameter proportional-integral-derivative (PID) controllers, but traditional PID control methods do not have the capabilities of self-optimization, self-adaptation, and self-learning, making it difficult to achieve and maintain optimal control system performance. In order to improve the transient response ability of the unit and the stability, safety and economy of the nuclear power plant, a model predictive control (MPC) strategy based on simultaneous perturbation stochastic approximation (SPSA) algorithm is proposed. In this method, MPC system is used to replace the traditional PID control system, and SPSA is used to optimize and set the parameters of the level control system, so as to optimize the performance of the SG level control system. The simulation results show that this method can effectively improve the setting efficiency of SG level control parameters and the stability of the control system. 
Keywords:
点击此处可从《核动力工程》浏览原始摘要信息
点击此处可从《核动力工程》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号