基于LabVIEW和Modbus的蒸汽发生器半实物仿真
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摘要
蒸汽发生器是压水堆核电站最重要的部件之一,其运行状态关系到整个核电站的安全,因此蒸汽发生器的建模与仿真对核电事业的发展有着重要的意义。文中针对压水堆核电站U型蒸汽发生器进行半实物仿真。通过分析U型蒸汽发生器的结构特点与运行原理,运用模块化建模的方法,对蒸汽发生器进行分块建模,并且将仿真数据存储于控制系统中。在LabVIEW软件中根据压水堆核电站蒸汽发生器的划分控制体的数学模型建立仿真模型,采用Modbus协议实现上位机仿真程序与实物端UW500集散系统的数据交互,以进行关键仿真数据采集。半实物仿真模型正确模拟了蒸汽发生器的运行,展现了蒸汽发生器一、二回路的热工参数变化,并在集散系统中存储记录。半实物仿真模型不仅可以用于不同工况的测试研究,也可以作为核电研究的教学展示。
Steam generator is one of the most important equipment of PWR nuclear power plant. The operating state of the steam generator is directly related to the safety of the entire nuclear power plant,so the modeling and simulation of steam generator is of great significance for the development of nuclear industry. This paper focused on the semi-physical simulation of PWR u-tube steam generator. By analyzing the structural characteristics and operation principle of the U-shaped steam generator,the steam generator was modeled by the modular modeling method,and the simulation data was stored in the control system. In LabVIEW software,the simulation model of steam generator in PWR nuclear power plant was established based on the mathematical model in divided control parts. The Modbus protocol was used to realize the communication between the software simulation in PC and UW500 distributed system for collecting important simulated data. The semi-physical simulation of steam generator correctly simulated the operation of steam generator,showed the change of thermal parameters in the first and second circuits of steam generator,and stored the records in the distributed system. These results proved that the semi-physical simulation model could be used not only for test research in different working conditions,but also as a teaching demonstration for nuclear power research.
Steam generator is one of the most important equipment of PWR nuclear power plant. The operating state of the steam generator is directly related to the safety of the entire nuclear power plant,so the modeling and simulation of steam generator is of great significance for the development of nuclear industry. This paper focused on the semi-physical simulation of PWR u-tube steam generator. By analyzing the structural characteristics and operation principle of the U-shaped steam generator,the steam generator was modeled by the modular modeling method,and the simulation data was stored in the control system. In LabVIEW software,the simulation model of steam generator in PWR nuclear power plant was established based on the mathematical model in divided control parts. The Modbus protocol was used to realize the communication between the software simulation in PC and UW500 distributed system for collecting important simulated data. The semi-physical simulation of steam generator correctly simulated the operation of steam generator,showed the change of thermal parameters in the first and second circuits of steam generator,and stored the records in the distributed system. These results proved that the semi-physical simulation model could be used not only for test research in different working conditions,but also as a teaching demonstration for nuclear power research.
引文
[1]郝祖龙,朱卉平.基于Lab VIEW和Simulink的蒸汽发生器水位控制分布式仿真[J].实验室研究与探索,2017,36(1):84-87.Hao Zulong,Zhu Huiping.Distributed simulation for water level control of steam generation using Lab VIEW and simulink[J].Research and Exploration in Laboratory,2017,36(1):84-87.
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[11]高李霞,喻丹萍,谭添才,等.蒸汽发生器传热管动态特性研究[J].核动力工程,2015,36(5):65-67.Gao Lixia,Yu Danping,Tan Tiancai,et al.Study on dynamic characteristics of heat transfer tube in SG[J].Nuclear Power Engineering,2015,36(5):65-67.
[12]Juhani Hyvarinen.Heat transfer characteristics of horizontal steam generator steam generators under natural circulation conditions[J].Nuclear Engineering and Design,1996(8):191-223.
[13]刘乐,黄禹,徐良旺.蒸汽发生器二次侧两相流传热特性数值研究[J].核科学与工程,2016,36(5):611-614.Liu Le,Huang Yu,Xu Liangwang.Numerical study on heat transfer characteristic of two-phase flow in SG secondary side[J].Nuclear Science and Engineering,2016,36(5):611-614.
[14]李娜,孙宝芝,张羽,等.核动力蒸汽发生器均相流模型及其动态仿真[J].电力建设,2013,34(9):10-15.Li Na,Sun Baozhi,Zhang Yu,et al.Homogeneous flow model and dynamic simulation of nuclear steam generator[J].Electric Power Construction,2013,34(9):10-15.
[15]邱桂辉.自然循环蒸汽发生器瞬态热工水力建模与分析[J].核科学与工程,2014,34(45):505-509.Qiu Guihui.Modeling and analysis of transient thermal hydraulic characteristic for natural circulation type steam generator[J].Nuclear Science and Engineering,2014,34(45):505-509.
[16]林桦,王云伟,张往锁.压水堆核电站功率控制系统对象研究及仿真分析[J].自动化仪表,2017,38(5):7-10.Lin Hua,Wang Yunwei,Zhang Wangsuo.Research and simulation analysis of power control system in pressurized water reactor nuclear power plant[J].Process Automation Instrumentation,2017,38(5):7-10.
[2]Rafa Laskowski,Janusz Lewandowski.A simplified mathematical model of a U-tube steam generator under variable load conditions[J].Archives of Thermodynamics,2013(9):75-88.
[3]陈佳跃.自然循环蒸汽发生器热工水力过程的数值仿真[D].广州:华南理工大学,2013.Chen Jiayue.Numerical simulation of natural circulation steam generator’s thermal-hydraulic process[D].Guangzhou:South China University of Technology,2013.
[4]张羽.蒸汽发生器数学建模及换热性能仿真[D].哈尔滨:哈尔滨工程大学,2013.Zhang Yu.Mathematical modelling and heat transfer performance simulation of steam generator[D].Harbin:Harbin Engineering University,2013.
[5]杨秋虎.基于Lab Windows/CVI的Modbus通信实现[J].电子科技,2015,28(2):150-151.Yang Qiuhu.Design of Modbus communication based on LabWindows/CVI[J].Electronic Science and Technology,2015,28(2):150-151.
[6]周文怡,方俊雅,朱子环.Lab VIEW与Modbus/TCP的伺服电机控制系统[J].测控技术,2015,34(3):83-84.Zhou Wenyi,Fang Junya,Zhu Zihuan.Control system of servo motor based on Lab VIEW and Modbus/TCP[J].Measurement and Control Technology,2015,34(3):83-84.
[7]杨建华,袁彪,胡晓娇,等.基于Lab VIEW的半实物虚拟仿真实验平台[J].电子产品世界,2017,10(1):39-40.Yang Jianhua,Yuan Biao,Hu Xiaojiao,et al.Haedware-in-the-Loop virtual simulation experiment platform based on Lab VIEW[J].Electronic Engineering and Product World,2017,10(1):39-40.
[8]邹海,李良,郑伟,等.立式自然循环蒸汽发生器机理建模与仿真研究[J].舰船科学技术,2017,39(3):113-115.Zou Hai,Li Liang,Zheng Wei,et al.Study of mechanism modeling and simulation of natural circulation steam generator[J].Ship Science and Technology,2017,39(3):113-115.
[9]邢海坤.U型管蒸汽发生器仿真模型及动态特性研究[D].北京:华北电力大学,2014.Xing Haikun.The simulation model and research on the dynamic characteristics of U-tube steam generator[D].Beijing:North China Electric Power University,2014.
[10]刘奕伽.蒸汽发生器的建模及仿真[J].油气田地面工程,2016,35(11):81-83.Liu Yijia.The modeling and simulation of steam generator[J].Oil-gas Field Surface Engineering,2016,35(11):81-83.
[11]高李霞,喻丹萍,谭添才,等.蒸汽发生器传热管动态特性研究[J].核动力工程,2015,36(5):65-67.Gao Lixia,Yu Danping,Tan Tiancai,et al.Study on dynamic characteristics of heat transfer tube in SG[J].Nuclear Power Engineering,2015,36(5):65-67.
[12]Juhani Hyvarinen.Heat transfer characteristics of horizontal steam generator steam generators under natural circulation conditions[J].Nuclear Engineering and Design,1996(8):191-223.
[13]刘乐,黄禹,徐良旺.蒸汽发生器二次侧两相流传热特性数值研究[J].核科学与工程,2016,36(5):611-614.Liu Le,Huang Yu,Xu Liangwang.Numerical study on heat transfer characteristic of two-phase flow in SG secondary side[J].Nuclear Science and Engineering,2016,36(5):611-614.
[14]李娜,孙宝芝,张羽,等.核动力蒸汽发生器均相流模型及其动态仿真[J].电力建设,2013,34(9):10-15.Li Na,Sun Baozhi,Zhang Yu,et al.Homogeneous flow model and dynamic simulation of nuclear steam generator[J].Electric Power Construction,2013,34(9):10-15.
[15]邱桂辉.自然循环蒸汽发生器瞬态热工水力建模与分析[J].核科学与工程,2014,34(45):505-509.Qiu Guihui.Modeling and analysis of transient thermal hydraulic characteristic for natural circulation type steam generator[J].Nuclear Science and Engineering,2014,34(45):505-509.
[16]林桦,王云伟,张往锁.压水堆核电站功率控制系统对象研究及仿真分析[J].自动化仪表,2017,38(5):7-10.Lin Hua,Wang Yunwei,Zhang Wangsuo.Research and simulation analysis of power control system in pressurized water reactor nuclear power plant[J].Process Automation Instrumentation,2017,38(5):7-10.