摘要
在大破口失水事故进程中 ,燃料包壳可能发生的破裂将导致流道部分阻塞 ,在事故分析中必须考虑由此产生的影响。用COBRA Ⅳ Ⅰ子通道程序详细分析了流道阻塞后的流场 ,改进了大破口失水事故分析软件包中燃料棒包壳温度分析程序FRAP T6 。
During the reflood phase of large break LOCA(Loss of Coolant Accident), the effect of flow blockage resulted from the rupture of hot rod cladding must be accounted for. Flow redistribution phenomena are analyzed systematically using COBRA Ⅳ Ⅰ computer code. The original flow redistribution model in FRAP T6(Fuel Rod Analysis Program——one of the codes in LBLOCA analysis package) is replaced by newly developed model and Chashma NPP LBLOCA is reanalyzed.
出处
《核科学与工程》
CSCD
北大核心
2000年第2期117-122,141,共7页
Nuclear Science and Engineering
