摘要
通过建立主冷却剂流量连续变化调节反应堆功率仿真模型,引入二回路负荷变化,对核反应堆热工水力瞬态过程进行分析研究,并与控制棒调节功率方案进行对比。结果表明:在低功率运行工况下,通过连续改变主冷却剂流量能够实现反应堆功率的调节,并满足反应堆热工安全性和机动性的要求。
The emulation model of reactor power regulation based on continuously changing the coolant flow rate was established, and the transient of nuclear power under rapidly power increasing condition of secondary loop was evaluated by means of emulate analysis code, the results were compared with reactor power regulation based on control rods. The simulation showed that the reactor power can be adjusted by changing the coolant flow rate continuously in low load range, and the method satisfy the requirements of reactor safety and mobility.
出处
《船海工程》
2013年第1期160-162,共3页
Ship & Ocean Engineering
关键词
核动力装置
主冷却剂流量连续变化
运行安全
nuclear power plant
continuously changing the coolant flow rate
operational safety