非能动核电站主给水丧失事故仿真研究

Simulation Research on Loss of Normal Feedwater for Passive Nuclear Power Plant

  • 摘要: AP1000非能动安全系统是一种新型的安全系统,无论从原理上还是系统布置上均与第2代核电站有区别,AP1000目前尚未实际运行,所以,其设计原理还需进一步深入地论证和分析。本文应用JTopmeret、THEATRe建模软件对AP1000非能动余热排出系统(PRHRS)、堆芯补水箱(CMT)系统进行仿真,验证在主给水丧失事故条件下PRHRS、CMT系统运行的可行性和应急堆芯冷却的有效性。结果表明:在事故条件下,PRHRS、CMT系统能够及时、有效地排出堆芯衰变热,保证堆芯的安全。此结论对AP1000电站的实际运行有一定的参考作用。

     

    Abstract: The passive safety system of AP1000 is a new type of safety system, which is different to the second generation nuclear power plant in principle and system layout. There is no actual operation experience of AP1000, therefore, the design principle of AP1000 still need be further verified and analyzed. This paper uses JTopmeret and THEATRe modeling software to carry out simulation on passive residual heat removal system (PRHRS) and core made tank (CMT) system of AP1000. The simulation object is to verify the feasibility and validity of PRHRS and CMT system during accidental conditions. The simulation results show that PRHRS and CMT system can discharge decay heat timely and effectively and guarantee safety of reactor core. The conclusions have reference value in helping operation of AP1000.

     

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