Analysis of severe core damage accident progression for the heavy water reactor  

作　　者：TONG Lili YUAN Kai YUAN Jingtian CAO Xuewu 

机构地区：[1]School of Mechanical Engineering, Shanghai Jiao Tong University', Shanghai 200240, China

出　　处：《Nuclear Science and Techniques》2010年第4期251-256,共6页核技术（英文）

摘　　要：In this study,the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis code.The selected accident sequences were multiple steam generator tube rupture and large break loss-of-coolant accidents because these led to severe core damage with an assumed unavailability for several critical safety systems.The progressions of severe accident included a set of failed safety systems normally operated at full power,and initiative events led to primary heat transport system inventory blow-down or boil off.The core heat-up and melting,steam generator response,fuel channel and calandria vessel failure were analyzed.The results showed that the progression of a severe core damage accident induced by steam generator tube rupture or large break loss-of-coolant accidents in a CANDU reactor was slow due to heat sinks in the calandria vessel and vault.In this study, the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis code. The selected accident sequences were multiple steam generator tube rupture and large break loss-of-coolant accidents because these led to severe core damage with an assumed unavailability for several critical safety systems. The progressions of severe accident included a set of failed safety systems normally operated at full power, and initiative events led to primary heat transport system inventory blow-down or boil off. The core heat-up and melting, steam generator response, fuel channel and calandria vessel failure were analyzed. The results showed that the progression of a severe core damage accident induced by steam generator tube rupture or large break loss-of-coolant accidents in a CANDU reactor was slow due to heat sinks in the calandria vessel and vault.

关 键 词：重水反应堆 损坏事故 蒸汽发生器 堆芯 CANDU堆 严重事故 热传输系统 事故分析 

分 类 号：TL423.064[核科学技术—核技术及应用] TQ116.11[化学工程—无机化工]