摘要
文章利用RETRAN-02/MOD 002程序对秦山核电厂主给水管断裂事故进行了敏感性分析研究。着重研究了蒸汽发生器及其传热模型、破口大小、停堆时间和辅助给水进入蒸汽发生器的时间对瞬变过程的影响,并分析了主给水管断裂事故的示例工况。文章给出了这些研究的主要结果。
The sensitivity studies of a main feedwater line rupture for Qinshan nuclearpower plant are performed with RETRAN-02/MOD 002. The studies place emph-asis on the primary to secondary heat transfer models of steam generator, breaksizes, credit taken for functioning of reactor trip and timing of auxiliary feedwatersupply to intact steam generator, A typical case of the main feedline rupturis analysed. This paper presents the main results of these studies.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
1989年第5期23-28,共6页
Atomic Energy Science and Technology
关键词
核电厂
给水管
断裂
事故
Nuclear power plant
Steam generator
Feedwater line rupture
Sensitivity study
