核电厂大破口事故建模与初始参数不确定性分析  

Large-break loss of coolant accident modeling and the uncertainty analysis of initial parameters

作　　者：殷煜皓[1] 林支康[1] 梁国兴[1] 匡波[1] 

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《扬州大学学报（自然科学版）》2012年第1期42-46,共5页Journal of Yangzhou University：Natural Science Edition

基　　金：国家自然科学基金资助项目(51076091)

摘　　要：以AP1000核电厂为原型,利用系统程序RELAP5建模模拟AP1000大破口失水事故,并与西屋公司大破口失水事故分析结果进行比较,另采用数学分析与灵敏度分析方法对电厂初始参数进行不确定性量化分析.比较结果显示:RELAP5和西屋公司的LBLOCA(large-break loss of coolant accident)计算结果有较好的一致性,而由数学分析和灵敏度分析处理电厂重要状态参数不确定性后,相对于保守的电厂参数包络LOCA(loss of coolant accident)分析,能额外提供30～50K的热工裕量.In this paper, AP1000 nuclear power plant is simulated by system code RELAP5 and AP1000 LBLOCA （large-break loss of coolant accident） is analyzed. Associated analysis provides contrast to the LBLOCA of Westinghouse AP1000. Besides, quantification of the effect of plant status uncertainty on safety parameter is performed based on mathematic statistics and sensitivity analysis. The results show that after sensitivity analysis and quantification of the plant status uncertainty, a greater PCT （peak cladding temperature） margin can be provided by 30-50 K than traditional conservative bounding status LOCA （loss of coolant accident） analysis.

关 键 词：核电厂 REALP5程序 大破口 状态参数不确定性 

分 类 号：TM623.91[电气工程—电力系统及自动化]