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首页> 外文期刊>Transactions of the American nuclear society >SAFETY ANALYSIS ON AP1000 CONTAINMENT COOLING SYSTEM RESPONSE UNDER LBLOCA CONDITIONS
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SAFETY ANALYSIS ON AP1000 CONTAINMENT COOLING SYSTEM RESPONSE UNDER LBLOCA CONDITIONS

机译:LBLOCA条件下AP1000容器冷却系统响应的安全性分析

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摘要

Large Break Loss of coolant Accident (LBLOCA) is one of the design basis accidents (DBAs) of nuclear power plant safety. DBAs may cause containment failure due to the impact of high temperature or high pressure resulted from the LB LOCAs. In this study, the passive cooling mechanism of AP1000 containment will be investigated, The performance of the passive containment cooling system (PCCS) is evaluated, and the decay heat removal capability for the long-term cooling is also evaluated in this study. Passive containment cooling system utilizes gravity driven natural convection and natural induced passive safety device to remove decay heat of fuels to the environmental atmosphere.
机译:冷却剂大断裂损失事故(LBLOCA)是核电厂安全的设计基准事故(DBA)之一。由于LB LOCA导致的高温或高压的影响,DBA可能导致密闭故障。在这项研究中,将研究AP1000安全壳的被动冷却机理,评估被动安全壳冷却系统(PCCS)的性能,并评估长期冷却的衰减散热能力。被动式安全壳冷却系统利用重力驱动的自然对流和自然感应式被动安全装置消除燃料向环境大气的衰减热。

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  • 来源
    《Transactions of the American nuclear society》 |2013年第6期|530-532|共3页
  • 作者单位

    Institute of Nuclear Engineering and Science,National TsingHua University Hsinchu,Taiwan,30013,R.O.C.;

    Institute of Nuclear Engineering and Science,National TsingHua University Hsinchu,Taiwan,30013,R.O.C.;

    Institute of Nuclear Engineering and Science,National TsingHua University Hsinchu,Taiwan,30013,R.O.C.;

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