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清华大学学报(自然科学版)  2018, Vol. 58 Issue (7): 658-663    DOI: 10.16511/j.cnki.qhdxxb.2018.26.033
  核能与新能源工程 本期目录 | 过刊浏览 | 高级检索 |
高温气冷堆核电站计算机化规程流程的建模和验证
徐晓娜, 黄晓津
清华大学 核能与新能源技术研究院, 先进核能技术协同创新中心, 先进反应堆工程与安全教育部重点实验室, 北京 100084
Modeling and verification of computerized procedures in high temperature gas-cooled reactor nuclear power plants
XU Xiaona, HUANG Xiaojin
Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing 100084, China
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摘要 为了满足高温气冷堆核电站计算机化规程流程验证的需要,针对高温气冷堆核电站"多个核蒸汽供应系统模块带一台汽轮机"的结构和运行特点,该文利用改进的着色Petri网建模方法,建立了常规规程执行流程模型和有中断的变体规程执行流程模型,并基于模型对计算机化规程执行进行了形式化验证。对一个典型的高温气冷堆核电站异常事件处理规程的案例进行分析,结果表明:基于改进着色Petri网的规程建模和验证方法有效,为高温气冷堆核电站计算机化运行规程系统的研制提供了重要的理论依据。
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关键词 高温气冷堆核电站计算机化规程建模和验证改进着色Petri网    
Abstract:The computerized procedures in high temperature gas-cooled reactor(HTGR)nuclear power plants need to be carefully monitored to efficiently control the operating characteristics of multiple nuclear steam supply system modules with one steam turbine. A normal execution process model and an interrupted variant execution process model were developed for HTGR power plants using the improved colored Petri net modeling method. The models were shown to accurately monior the execution of the computerized procedures. An analysis of a typical abnormal operating procedure for an HTGR plant shows that the modeling and verification based on the colored Petri net is effective and provides a theoretical foundation for the development of HTGR control systems.
Key wordshigh temperature gas-cooled reactor (HTGR)    modeling and verification of computerized procedures    improved colored Petri net
收稿日期: 2017-12-14      出版日期: 2018-07-15
基金资助:国家重大专项经费资助项目(ZX06901)
通讯作者: 黄晓津,研究员,Email:huangxj@tsinghua.edu.cn     E-mail: huangxj@tsinghua.edu.cn
引用本文:   
徐晓娜, 黄晓津. 高温气冷堆核电站计算机化规程流程的建模和验证[J]. 清华大学学报(自然科学版), 2018, 58(7): 658-663.
XU Xiaona, HUANG Xiaojin. Modeling and verification of computerized procedures in high temperature gas-cooled reactor nuclear power plants. Journal of Tsinghua University(Science and Technology), 2018, 58(7): 658-663.
链接本文:  
http://jst.tsinghuajournals.com/CN/10.16511/j.cnki.qhdxxb.2018.26.033  或          http://jst.tsinghuajournals.com/CN/Y2018/V58/I7/658
  图1 氦风机误加速异常事件处理规程执行流程
  图2 规程执行流程
  图3 着色 Petri网
  图4 改进着色 Petri网模型
  表1 二回路给水管道破口异常事件处理规程主要处理过程
  表2 正常启动规程主要流程
  图5 基于改进着色 Petri网的二回路给水管 道破口异常事件处理规程
  图6 基于改进着色 Petri网的正常启动规程主要步骤
  图7 基于改进着色 Petri网的二回路给水管道破口 异常处理规程前2个步骤模型
  图8 基于改进着色 Petri网的二回路给水管道破口 异常处理规程前2个步骤模型可达标识图
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