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核电厂反应堆冷却剂泵惰走流量测量试验优化 被引量:1

Optimization of Idle Flow Measurement Test of Reactor Cooling Pump in Nuclear Power Plant
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摘要 机组调试及运行期间均需定期执行反应堆冷却剂泵惰走流量测量试验,试验要求实施临时控制变更直接断开主泵6.6 kV开关以达到试验执行条件。由于该变更涉及主泵的启停,实施临时控制变更的方式选择不当会极大地增加失败风险。某电厂M310机组曾出现在临时控制变更恢复过程中导致汽动辅助给水泵误启的运行事件,根据该电厂在历史执行过程中出现的偏差并结合同行电厂经验反馈,对事件中的停泵方式优劣点进行分析,为后续各电厂执行试验时提供借鉴。 During commissioning and operation of the unit,the idleflow measurement test of the reactor coolant pump shall be performed regularly.The test requires temporary control change to directly disconnect the main pump 6.6 kV switch to meet the test execution conditions.Since the change involves the start and stop of the main pump,the wrong way to implement the temporary control change will greatly increase the risk of the test.The M310 unit in apower plant once encountered an operating event that caused the steam-driven auxiliary feedwater pump to start incorrectly during the restoration of temporary control changes.Based on the deviations in the historical execution of the power plant and combined with feedback from peer power plants,the pros and cons of the pump-stopping methods in the incident are analyzed to provide reference for subsequent power plants to perform tests.
作者 陈星玥 高原 李振 CHEN Xingyue;GAO Yuan;LI Zhen(Fujian Fuqing Nuclear Power Co.,Ltd.,Fuqing 350318,China)
出处 《电工技术》 2021年第17期155-156,161,共3页 Electric Engineering
关键词 惰走反应 堆冷却剂泵 临时控制变更 汽动辅助 给水泵 idle reactor reactor coolant pump temporary control changes steam assisted feed pump
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