期刊文献+

AP1000核电厂二回路主管道双端断裂流体喷射力计算分析 被引量:3

Calculation and Analysis of Fluid Dynamic Thrust Force in Main Piping Double-ended Break of AP1000 Secondary Loop
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摘要 AP1000是先进的第三代压水堆核电厂,为确保核电厂在事故工况下的安全性,需对二回路主管道发生双端断裂的工况进行研究。本文采用RELAP5/MOD3.4软件对核电厂二回路突发主管道双端断裂的事故工况进行了数值模拟,计算得到断裂后管道破口处的喷放流量、压强、空泡份额及喷射力等物理参数的变化特性,并将计算结果与ANSI 58.2简化计算方法的结果进行了比较分析。结果表明,RELAP5/MOD3.4计算所得的喷射力小于简化计算方法所得结果。本文分析结果为进行AP1000核电厂的破裂管道甩击防护提供了基础。 AP1000is the advanced third-generation pressurized water reactor nuclear power plant(NPP).To ensure the safety of NPP under accident condition,it is necessary to study the characteristics of the main piping of the secondary loop when doubleended break condition occurred.The RELAP5/MOD3.4code was used to carry out numerical simulation of the NPP secondary loop under double-ended break condition.The calculation results were obtained,which included the spray flow rate,pressure,void fraction,dynamic thrust force and other parameters of the piping breach,as well as the changing characteristics of those parameters.The calculation results of RELAP5/MOD3.4were compared with the results calculated by ANSI 58.2simplified algorithm.And it turns out that the dynamic thrust forces derived from the calculation results ofRELAP5/MOD3.4are smaller than those of ANSI 58.2simplified algorithm.The analysis of this paper lays out the basic foundation for piping whip restraint design due to piping break for AP1000 NPP.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第2期297-303,共7页 Atomic Energy Science and Technology
基金 国家科技重大专项资助项目(2008ZX06002001-11)
关键词 AP1000核电厂 二回路主管道 双端断裂 喷射力计算 AP1000 nuclear power plant secondary loop main piping double-ended break dynamic thrust force calculation
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参考文献7

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