Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR
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摘要: 以日本超临界水冷堆(Super LWR)为背景,建立相关数学物理模型,计算分析超临界水冷堆在部分丧失给水瞬态下,主泵惰转时间、紧急停堆延迟时间和密度反馈比对最高包壳温度的影响。分析结果表明:部分丧失给水后,在主泵惰转和反应堆紧急停堆的共同作用下,最高包壳温度先是快速升高,然后快速下降;延长惰转时间能延缓冷却剂流量的减少,从而延缓最高包壳温度的升高;紧急停堆延迟时间越短,越能减缓最高包壳温度的升高;密度反馈比的变化对包壳的温度影响不大。可见,主泵惰转时间、紧急停堆延迟时间能对堆芯的安全性能产生明显的影响。Abstract: Taking the Super LWR concept proposed by Japanese as the background,relevant mathematical and physical calculation models are built,and the effect of coast-down time of primary pump,scram delay and ratio of density coefficient on the maximum cladding surface temperature（MCST） is evaluated.The results show that: after the transient of partial loss of reactor coolant flow,due to the pump seize and reactor scram,the maximum cladding temperature increases quickly at first and then declines rapidly;extending the coast-down time of primary pump can delay the reduction in the flow of coolant,thereby delaying the increasing of maximum cladding temperature;scram delay is the shorter,thereby better slow down the maximum cladding temperature;Ratio of density coefficient affects the maximum cladding temperature changes a little.Visibly,the coast-down time of primary pump or the scram delay can be a significant impact on the safety performance of the core.
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