摘要
阳江核电厂1号机组给水调节阀均由FISHER换型为MASONEILAN后,由于旁路给水控制系统参数与实际情况不符,直接造成蒸汽发生器液位剧烈波动,进而触发跳堆事件。优化主给水控制系统(ARE)控制逻辑中ARE407/408/409RG(小阀控制曲线函数)曲线函数,通过优化控制函数的方式来弥补现场设备与控制逻辑不符的情况,实现蒸汽负荷与给水流量的匹配。优化后与参考机组对比可发现,机组正常升功率经过大小阀切换点与30%FP(FP为满功率)平台大小阀切换试验过程中蒸汽发生器液位扰动情况,阳江1号机组试验结果明显优于参考机组。
After the replacement of FISHER by MASONEILAN to regulate the feedwater valve in Unit 1 of Yang Jiang Nuclear Power Plant, the parameters of the feed water bypass control system does not match the actual situation, and it directly results in the steam generator water level fluctuations, and thus brings the reactor trip. The control logic ARE407/408/409RG (small valve control function curve) curve function in ARE system is optimized, and the steam load and the discharge of water is matched by optimizing the control function to compensate for the inconsistent of field devices and control logic. Comparison of optimized and reference units showed that for the steam generator level disturbance at the switchover point for the small and large valves during the normal power rising and during the valve switchover test for 30%FP platform, the test result in Unit 1 of Yang Jiang Nuclear Power Plant is significantly better than that for the reference unit.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2016年第4期87-89,共3页
Nuclear Power Engineering
关键词
跳堆
方案
优化
校验
Reactor Trip, Scheme, Optimization, Verification