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压水堆核电厂过冷度显示的仿真
Simulation of Core Subcooling Display System in PWR Nuclear Power Plant
【摘要】 清华大学核电厂模拟培训中心模拟机的参考电厂是美国西屋公司设计的,其模型中没有堆芯过冷度显示系统的模拟。根据三哩岛事故的教训,在该装置上增设过冷度显示的模拟是十分必要的。本文叙述了在原模拟机上增设过冷度显示所进行的软件设计、数据传输和显示线路设计。
【Abstract】 The reference plant of the simulator in Tsinghua University Nuclear Power Plant Training Center was designed by Westinghouse Company, USA. There was no simulation of Core Subcooling Display System(CSDS). According to the experence of “Three-Mile Island Accident”,it is quite necessary to add the core subcooling display simulation to the unit. In this topic, the modeling, data transferring and display circuit designing of CSDS simulation are described.
【基金】 国家“七五”攻关项目
- 【文献出处】 核动力工程 ,NUCLEAR POWER ENGINEERING , 编辑部邮箱 ,1995年05期
- 【分类号】TM623
- 【下载频次】47