电子科技 ›› 2019, Vol. 32 ›› Issue (2): 75-79.doi: 10.16180/j.cnki.issn1007-7820.2019.02.016

• • 上一篇    

基于LabVIEW和Modbus的蒸汽发生器半实物仿真

陈伟,王亚刚   

  1. 上海理工大学 光电信息与计算机工程学院,上海 200093
  • 收稿日期:2018-06-14 出版日期:2019-02-15 发布日期:2019-01-02
  • 作者简介:陈伟(1993-),男,硕士研究生。研究方向:模式识别与智能系统。|王亚刚(1967-),男,博士,教授。研究方向:系统辨识、先进过程控制。
  • 基金资助:
    国家自然科学基金青年基金(11502145)

Semi-physical Modeling of Steam Generator Based on LabVIEW and Modbus

CHEN Wei,WANG Yagang   

  1. School of Optical Electrical and Computer Engineering,University of Shanghai for Science and Technology, Shanghai 200093,China
  • Received:2018-06-14 Online:2019-02-15 Published:2019-01-02
  • Supported by:
    The Young Scientists Fund of the National Natural Science Foundation of China(11502145)

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。

关键词: 压水堆核电站, 蒸汽发生器, LabVIEW, Modbus, UW500集散系统, 热工参数

Abstract:

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.

Key words: PWR, steam generator, LabVIEW, Modbus, UW500 distributed system, thermal parameter

中图分类号: 

  • TP273
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