摘要
在主给水管道破裂事故下,利用RELAP5/MOD3.4程序对CPR1000压水堆一回路热工水力参数瞬态特性进行分析计算,验证采用空冷换热器的CPR1000二次侧非能动应急热阱对事故的缓解能力。计算结果表明:CPR1000在发生主给水管道破裂事故后,二次侧非能动应急热阱完全可及时向蒸汽发生器补水,同时导出堆芯余热,保证反应堆处于安全状态,从而验证了CPR1000二次侧非能动应急热阱的设计是成功的。
The transient thermal hydraulic characteristics of CPR1000 were analyzed using RELAP5/MOD3.4 to verify the capability of the adopting air-cooled heat exchanger＇s emergency passive heat sink （EPHS） for accident mitigation under the con- dition of feed-water line break （FLB）. The calculation results show that the EPHS of CPR1000 can supply the water to steam generator immediately and remove the core residual heat after the FLB successfully. Therefore, it demonstrates that the design of the EPHS of CPR1000 is successful.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第3期321-327,共7页
Atomic Energy Science and Technology
