主蒸汽管道断裂事故分析

Major Steam Line Break Accident Analysis

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ＦＬＩＣＡⅢＦ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）

During the analyses of Daya Bay Nuclear Power Plant reload,the major steam line break accident must be studied because the Doppler power feedback coefficients exceed the limiting value.This report analyzes the major steam line break accident of Daya Bay Nuclear Power Station unit 1 cycle 5 using THEMIS code and FLICA Ⅲ code.The result shows that no departure from nucleate boiling occurs for any break assuming the most negative value rod cluster control assembly stuck in its full withdrawn position.