Design and Verification of Virtualization Transplantation Method for Distributed Control System

Expand
  • Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China

Online published: 2020-04-08

Abstract

Virtualization transplantation technologies of distributed control system (DCS) include simulation, emulation and stimulation. Based on emulation, a set of technology solution for virtualization transplantation of DCS architecture and field control station was proposed. Similarities and differences between the actual control system and virtual DCS based on virtualization system architecture were also analyzed. Therefore, the communication mechanism of the virtualization system was optimized to improve the emulation performance. Moreover, a nuclear reactor power regulation system was taken as an example. By comparing actual control system and emulation system under related application functions, the trend of curve of related parameters is basically the same, and the results proved that the method of virtualization transplantation can be applied to practical projects.

Cite this article

PENG Hao,ZHANG Xu,DENG Zhiguang,JIANG Wei,LIU Mingming,ZHANG Yu,LIU Guohai . Design and Verification of Virtualization Transplantation Method for Distributed Control System[J]. Journal of Shanghai Jiaotong University, 2019 , 53(Sup.1) : 118 -122 . DOI: 10.16183/j.cnki.jsjtu.2019.S1.021

References

[1]杨诗茹. 虚拟DCS组态环境的设计与开发[D]. 保定: 华北电力大学, 2016. YANG Shiru. Design and development of configuration environment of virtual DCS[D]. Baoding: North China Electric Power University, 2016. [2]国家能源局.核电厂操纵人员培训及考试用模拟机: NB/T 20015—2010[S].北京: 原子能出版社, 2010. National Energy Administration. Nuclear power plant simulators for use in operator training and examination: NB/T 20015—2010[S]. Beijing: Atomic Energy Press, 2010. [3]华伟. 600 MW超临界机组仿真机设计与开发[D]. 保定: 华北电力大学, 2007. HUA Wei. Design and development of simulator on 600 MW super-critical unit[D]. Baoding: North China Electric Power University, 2007. [4]张旭, 徐海燕, 王恺, 等. 核安全级仪控仿真系统的接口设计[J]. 现代计算机, 2019(17): 69-72. ZHANG Xu, XU Haiyan, WANG Kai, et al. Interface design of safety-class instrument control simulation system[J]. Modern Computer, 2019(17): 69-72. [5]高汉军, 曲鸣, 李青, 等. 核电站分布式系统虚拟过程控制平台设计研究[J]. 计算机仿真, 2017, 34(2), 144-149. GAO Hanjun, QU Ming, LI Qing, et al. Research and design on virtual DCS process control plat-form in nuclear power plant[J]. Computer Integrated Manufacturing Systems, 2017, 34(2): 144-149. [6]孙远志, 张洋, 庞智, 等.应用全范围仿真机的核电站仪控软件设计验证[J]. 计算机仿真, 2014, 31(4): 147-150. SUN Yuanzhi, ZHANG Yang, PANG Zhi, et al. A validation and verification method of I&C software of nuclear power station based on FSS[J]. Computer Integrated Manufacturing Systems, 2014, 31(4): 147-150. [7]LIN M, YANG Z W, HOU D, et al. Applying engineering simulator to verification and validation of di-gital I&C in nuclear power plant[C]//International Conference on Nuclear Engineering. Brussels, Belgium: ASME, 2009: 729-733. [8]HOU D, LIN M, XU Z H, et al. Development and application of an extensible engineering simulator for NPP DCS closed-loop test[J]. Annals of Nuclear Energy, 2011, 38(1): 49-55. [9]王国旭, 吴婕, 曾碧凡, 等. 模型预测控制在压水堆堆芯功率控制中的应用[J]. 原子能科学技术, 2017, 51(3): 480-484. WANG Guoxu, WU Jie, ZENG Bifan, et al. Model predictive control method for core power control in pressurized water reactor[J]. Atomic Energy Science and Technology, 2017, 51(3): 480-484. [10]邓志光, 吕鑫, 简一帆, 等. 基于SCADE开发的SDMC在堆芯功率控制中的应用[J]. 自动化仪表, 2019, 40(4): 103-106. DENG Zhiguang, LYU Xin, JIAN Yifan, et al. Application of SDMC developed based on SCADE in core power control[J]. Process Automation Instrumentation, 2019, 40(4): 103-106. [11]ZHANG X, DENG Z G, LI J, et al. Design and ve-rification of reactor power control based on stepped dynamic matrix controller[J]. Science and Technology of Nuclear Installations, 2019, 2019: 1-11.doi: 10.1155/2019/4973120.
Outlines

/