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Functional Failure Analysis for Passive Containment Cooling System in AP1000

机译:AP1000被动安全壳冷却系统功能故障分析

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摘要

More and more attention is paid to probability safety assessment (PSA) especially after several severe accidents in nuclear power development and PSA has been widely used now for nuclear power plant safety evaluation, design update and so on, system reliability analysis is one of the important aspects in PSA. In order to improve the safety of new generation nuclear power plant, passive containment cooling system is innovatively used in AP1000 reactor design (Ref.1), which is an important safety-related system. By this system heat produced in the reactor can be transferred to the heat sink - atmosphere depending on natural circulation, but not on the human behaviors or the operation of other equipments (Ref. 2,3).
机译:概率安全评估(PSA)越来越受到重视,尤其是在核电开发中发生了几起严重事故之后,PSA目前已广泛用于核电厂的安全评估,设计更新等,系统可靠性分析是重要的内容之一。 PSA中的各个方面。为了提高新一代核电站的安全性,AP1000反应堆设计中创新地使用了被动安全壳冷却系统(参考文献1),这是与安全相关的重要系统。通过该系统,反应堆中产生的热量可以转移到散热器-大气中,这取决于自然循环,而不取决于人类行为或其他设备的运行(参考文献2,3)。

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  • 来源
    《Transactions of the American nuclear society》 |2013年第6期|547-549|共3页
  • 作者单位

    School of Nuclear Science and Engineering State Key Laboratory of Alternate Electrical Power System with Renewable Energy Sources,North China Electric Power University No.2 Beinong Road,Huilongguan,Changping District,Beijing,China,102206;

    School of Nuclear Science and Engineering State Key Laboratory of Alternate Electrical Power System with Renewable Energy Sources,North China Electric Power University No.2 Beinong Road,Huilongguan,Changping District,Beijing,China,102206;

    School of Nuclear Science and Engineering State Key Laboratory of Alternate Electrical Power System with Renewable Energy Sources,North China Electric Power University No.2 Beinong Road,Huilongguan,Changping District,Beijing,China,102206;

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