三门核电一回路热段冷却剂流量补偿方法分析与优化

Analysis and optimization of coolant flow compensation method in hot section of Sanmen Nuclear Power primary circuit

三门核电1#、2#机组应用归一化方法对一回路热段冷却剂进行流量补偿,保证热段流量在误差允许范围内,避免反应堆因此停堆。对目前的方法和执行过程存在的问题进行了分析,提出了通过验证参数简化补偿平台等手段对其进行优化,在大修过程中对最终方案进行了验证,有效节省了机组升功率时间,降低了参数写入保护和安全监控系统的风险。针对最终方案提出了进一步优化方向,对后续方案升级及优化起借鉴作用。

The 1# and 2# nuclear plant unit of Sanmen Nuclear Power apply the normalized method to compensate the coolant flow in the hot leg of the primary circuit, so as to ensure the flow in the hot leg is within the allowable error range and avoid the reactor trip. In this paper, the current methods and the problems existing in the implementation process are analyzed. The optimization method is proposed by verifying the parameter simplification compensation platform, and the final scheme is verified in the overhaul process, which effectively saves time in lifting power of unit and reduces the risk of sending parameter to Protection and Safety Monitoring System. The further optimization direction of the final scheme is put forward, which can be used for reference to upgrade and optimize the subsequent scheme.