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在大亚湾核电站换料分析中,针对多卜勒功率亏损超限,需要对主蒸汽管道断裂事故进行分析。本文利用THEMIS程序和FLICAⅢF程序对大亚湾核电站一号机组第五循环换料分析中的主蒸汽管道断裂事故进行了计算分析。其结果表明:在主蒸汽管道断裂事故过程中,即使最大价值的一组控制棒完全卡在堆顶也不会发生偏离泡核沸腾(DNB)
In Daya Bay Nuclear Power Station refueling analysis, in view of Doppler power loss overrun, the main steam pipeline fracture accident needs to be analyzed. In this paper, the THEMIS program and FLICAⅢ-F program was used to calculate and analyze the main steam pipeline fracture in the fifth cycle refueling analysis of Daya Bay Nuclear Power Station. The results show that even in the event of a main steam pipeline rupture, a deviation from nucleate boiling (DNB) does not occur even if the maximum value of a set of control rods is completely stuck at the top of the pile.