摘要
采用计算流体力学有限元方法,对核电厂压力容器和蒸汽发生器之间反应堆冷却剂管道进行了稳态分析,旨在模拟核电站正常工况下的反应堆冷却剂管道流体状态,为管道测量仪表的选型、设计和制造提供参考,为控制系统的架构提供数据支持。
This paper uses computational fluid dynamics(CFD) to analysis the reactor coolant pipe of nuclear power plant which lies between reactor pressure vessel and steam generator to simulate the steady-state of reactor coolant when the plant is in normal operation. The results can provide reference for instrument selection, design and manufacturing and give data support for control system.
引文
1郑明光,杜圣华.压水堆核电站工程设计[M].上海:上海科学技术出版社,2013. 149~152.
2 王福军.计算流体动力学分析——CFD软件原理及应用[M].北京:清华大学出版社,2004.2~3.
3 韩占忠,王敬,兰小平.FLUENT流体工程仿真计算实例与应用[M].北京:北京理工大学出版社,2004.6.