期刊文献+

“华龙一号”数字化堆芯控制系统设计与改进

Design and improvement of digital core control system for HPR1000
下载PDF
导出
摘要 压水堆核电厂堆芯控制系统主要实现反应堆冷却剂平均温度控制、反应堆功率控制等重要功能。数字化技术的普及为控制系统带来了更精准的控制能力、更稳定的运行能力,但同时也带来了新的挑战与风险。应用数字技术带来的质量位、缺省值、交叉比较等全新功能,若未进行合理的配置,反而会使在运的控制系统产生偏离控制的后果。以漳州核电1号机组(华龙一号)数字化堆芯控制系统为例,通过对其设计功能的研究,识别出现有设计存在的缺陷,进而提出了相应的改进方案。同时为数字化堆芯控制系统的后续优化给出了建议,可为新建压水堆核电厂数字化堆芯控制系统在系统设计阶段提供一定的借鉴与参考。 The core control system of PWR nuclear power plant mainly realizes the average temperature control of reactor coolant,reactor power control and other important functions.The popularization of digital technology brings more accurate control ability and more stable operation ability to the control system,but it also brings new challenges and risks.If the new functions brought by digital technology such as mass bit,default value and crosscomparison are not properly configured,the control system in operation will deviate from the control result.This paper takes the digital core control system of Zhangzhou No.1 Nuclear Power Unit(HPR1000)as an example,through the study of its design function,identifies the design defects,and then puts forward the corresponding improvement plan.At the same time,some suggestions are given for the subsequent optimization of the digital core control system,which can be used for reference in the system design stage of new PWR nuclear power plants.
作者 何程 何明智 陆炜伟 He Cheng;He Mingzhi;Lu Weiwei(CNNP Guodian Zhangzhou Energy Co.,Ltd.,Zhangzhou 363300,China)
出处 《电子技术应用》 2023年第S01期67-71,共5页 Application of Electronic Technique
关键词 数字化堆芯控制系统 冷段温度 交叉比较 缺省值 digital core control system cold section temperature cross comparison default value
  • 相关文献

参考文献2

共引文献15

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部