核电厂堆芯冷却恶化恢复安注措施研究

发布时间：2018-05-12 15:57

  本文选题：堆芯冷却恶化 + 恢复安注措施　； 参考：《核科学与工程》2017年05期

【摘要】：本文使用RELAPSCDAPSIM3.4程序建立核电厂事故分析模型,选取了典型的中、小冷段破口事故作为分析序列,针对堆芯冷却恶化现象采取恢复安注措施进行了详细的热工水力计算。着重分析了在辅助给水有效情况下,重启安注的时间窗口、启动上充应对安注失效情况下的有效性、有无安注箱注入敏感性等。分析结果表明:当堆芯出口温度超过923K(即650℃),恢复安注建立应急堆芯冷却流量措施对于中、小破口是有效的;启动上充对较小破口效果明显;安注箱有效注入对中破口冷却恶化事故缓解有重要作用。
[Abstract]:In this paper, the accident analysis model of nuclear power plant is established by using RELAPSCDAPSIM3.4 program, and the typical middle and small cold section break accident is selected as the analysis sequence, and the thermal hydraulic calculation is carried out in detail according to the deterioration of core cooling. In the case of auxiliary water supply efficiency, the time window of restarting the injection is restarted, the effectiveness of the supercharge response to the failure of the injection, the sensitivity of the injection box and so on are analyzed. The results show that when the core outlet temperature exceeds 923K (i.e. 650 鈩，

本文编号：1879230