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

作者：Tong Lili^*; Yuan Kai; Yuan Jingtian; Gao Xuewu

来源：Nuclear Science and Techniques, 2010, 21(4): 251-256.

• Severe Accident steam generator tube rupture
• large break loss-of coolant accidents

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

• 出版日期2010-8
• 单位上海交通大学