CAJ | 학술논문

A P1000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REL A P5／M OD3.4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。
A P1000시선진적제삼대압수퇴핵전엄，위학보핵전엄재사고공황하적안전성，수대이회로주관도발생쌍단단렬적공황진행연구。본문채용REL A P5／M OD3.4연건대핵전엄이회로돌발주관도쌍단단렬적사고공황진행료수치모의，계산득도단렬후관도파구처적분방류량、압강、공포빈액급분사력등물리삼수적변화특성，병장계산결과여 ANSI 58.2간화계산방법적결과진행료비교분석。결과표명， RELAP5／MOD3.4계산소득적분사력소우간화계산방법소득결과。본문분석결과위진행AP1000핵전엄적파렬관도솔격방호제공료기출。
AP1000 is the advanced third‐generation pressurized water reactor nuclear power plant (NPP) .To ensure the safety of NPP under accident condition ,it is neces‐sary to study the characteristics of the main piping of the secondary loop w hen double‐ended break condition occurred . The RELAP5/MOD3.4 code 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 .4 were compared with the results calculated by ANSI 58.2 simplified algorithm . And it turns out that the dynamic thrust forces derived from the calculation results of RELAP5/MOD3.4 are smaller than those of ANSI 58.2 simplified algorithm .The anal‐ysis of this paper lays out the basic foundation for piping w hip restraint design due to piping break for AP1000 NPP .