稠密栅堆芯大破口失水事故特性分析  

Study on Analysis Methods and Characteristics of Large Break Loss of Coolant Accident of Reactor Cores with Tight Lattice Design

作　　者：黄代顺[1] 付冉[1] 申亚欧[1] 吴丹[1] 余红星[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《核动力工程》2014年第2期17-20,共4页Nuclear Power Engineering

基　　金：国家自然科学基金项目资助(11275178)

摘　　要：稠密栅堆芯的应用涉及到的关键性问题之一是在破口事故下的应急冷却。应用改进程序RELAP5/TIGHT计算和分析两组不同设计方案下的稠密栅堆芯在破口事故下的特性,结果表明:稠密栅堆芯相比普通堆芯,破口事故持续时间更长;再淹没阶段的包壳峰值温度相比喷放阶段的包壳峰值温度更高;堆芯燃料棒中心距与燃料棒外径比值(p/d)对于包壳峰值温度的影响很大;堆芯功率密度的提高会使得对安注流量的需求大大增强。从安全分析的角度来看,不推荐堆芯p/d设计小于1.10。A key problem related with the tight lattice core design is whether it could be cooled successfully in a loss of coolant accident （LOCA）. In this paper, the modified code RELAP5/TIGHT was used to calculate and analyze the characteristics of large break loss of coolant accident of reactor cores with two different tight lattice design. It was found that compared with standard reactor core designs, the transient progress of a LOCA accident lasted a longer time for a tight lattice core design; the peak cladding temperature in the refiooding phase was much higher than that in the blown-down phase; the ratio of center distance between fuel rods to outer diameter of fuel rod （p/d） has a great impact on the peak cladding temperature; the increasing in the power density results in the increasing need to the safety injection flowrate. For safety consideration, p/d ratio less than 1.10 is not recommended.

关 键 词：稠密栅 破口事故 RELAP5 TIGHT 包壳峰值温度 

分 类 号：TL33[核科学技术—核技术及应用]