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压水堆核电站LOCA事故最大上充流量的数值研究

Numerical Investigation of Maximum Charging Flowrates under Large Break Loca Accident Condition in PWR Nuclear Power Plant
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摘要 本文采用计算流体软件Flowmaster7.5针对大亚湾核电站化学和容积控制系统与硼和水补给系统进行了模拟。通过将正常工况下的模拟计算结果与设计参考值进行对比,验证模型的可靠性。并根据所建模型,在LOCA事故发生后,启动不同数目的上充泵对一回路进行充水,研究最大上充流量与一回路压力之间的关系。 Chemical and Volume Control System and Reactor Boron and Water Makeup System of Daya Bay Nuclear Power Plant arc simulated with Computational Fluid Dynamic Software Flo,mnasterV7.5, and the model is validated with design data. According to the model, after LBLOCA takes place, the relation between maximum charging flowrates and Reactor Coolant System pressure is predicted, and different numbers of charging pumps are simulated and compared.
出处 《科技信息》 2012年第19期71-73,共3页 Science & Technology Information
关键词 压水堆 化学和容积控制系统(RCV) 硼和水补给系统(REA) LOCA事故 Pressurized water reactor (PWR) Chemical and volume control system Reactor boron and water makeup system LBLOCA
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参考文献2

  • 1陈济东.大亚湾核电站系统及运行:上册[M]北京:原子能出版社,1994.
  • 2朱继洲.压水堆核电厂的运行[M]北京:原子能出版社,2000.

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