摘要
国内某核电厂CPR机组常规岛主给水流量控制系统主要用于控制向蒸汽发生器的给水流量,保证蒸汽发生器二回路侧水位维持在一个随汽轮机负荷变化的整定值上。基于SolidWorks仿真软件关于CPR核电机组主给水流量调节阀铜套与驱动杆剧烈磨损的仿真分析,对主给水流量控制阀门解体过程中所出现的铜套与驱动杆硬质合金剧烈磨损,以及预紧弹簧弯曲等问题进行展开。
The conventional island main feed water flow control system of CPR unit in a domestic nuclear power plant is mainly used to control the feed water flow to the steam generator to ensure that the water level at the second circuit side of the steam generator is maintained at a setting value that varies with the air load.Based on the simulation software SolidWorks on the intense wear of copper sleeve and driving rod of the main feed water flow control valve of CPR nuclear power unit-the intense wear of copper sleeve and the hard alloy of driving rod in the disintegration process of the main feed water flow control valve,as well as the bending of the pre-loaded spring and other problems are carried out.
作者
汪顺利
马成
邹志林
马恒亮
彭军
Wang Shun-li;MA Cheng;ZOU Zhi-lin(CGN Nuclear Power Operation Co.,Ltd.)
出处
《电站系统工程》
2024年第1期54-56,共3页
Power System Engineering