压水堆部分堆芯参数敏感性分析  

The Sensitivity Study of Severe Accident

作　　者：郎明刚[1] 高祖瑛[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《核科学与工程》2002年第2期104-107,共4页Nuclear Science and Engineering

摘　　要：用估计严重事故原理的整体型第二代轻水堆电站风险评价工具MELCOR程序,以在建的岭澳核电站为对象,分析了压水堆部分堆芯参数的不确定性和敏感性。这些参数是燃料元件孔隙度,熔渣孔隙度,熔渣到下封头贯穿件的传热系数。把分析结果与相应的沸水堆参数的敏感性分析结果进行比较,发现核电站发生全厂断电事故时,事故进程对堆芯输入参数不敏感。MELCOR, a fully integrated computer code of the 2nd generation probabilistic risk assessment tool for NPPsis used, in sensitivity studies on several input parameters of a PWR core model referenced to the Ling'ao nuclear power plant. These parameters are the fuel and cladding porosities, the debris porosity, the heat transfer coefficient between the debris and the lower-plenum penetration. The analysis results were compared with those of a BWR core model. During a station blackout accident of LWR its procedure is not sensitive to the core input parameters.

关 键 词：压水堆 堆芯参数 敏感性 严重事故 MELCOR 不确定性 

分 类 号：TL421.1[核科学技术—核技术及应用] TL364.4