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Numerical study on improved design of passive residual heat removal system for China pressurizer reactor

机译:中国压力机反应器被动残留散热系统改进设计的数值研究

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摘要

The core residual heat removal system of the pressurized water reactor (PWR) is a vital facility to ensure the reactor safety, and its failure after shutdown will inevitably lead to the meltdown of the core. However, the existing core residual heat removal system of CPR1000 only guarantee the 72-hour grace period, after which the core decay heat can still melt the core within one day. The present study proposes an improved design of passive residual heat removal system (PRHRS) that utilizes natural forces to realize a passive self-start. Meanwhile, an innovative method is also proposed to use the atmosphere as the final heat sink in this paper. Subsequently a numerical study is conducted to verify the performance of the improved design during accident condition. Numerical results show that the improved design of PRHRS maintains a timeless safety cooling capacity during the station blackout (SBO) scenario. Finally, the parameter sensitivity study is performed to investigate a reasonable design value of chimney height. And numerical results prove that the proposed PRHRS is still capable of removing the core residual heat continuously even if the atmosphere temperature is variable. All component functions of new designed PRHRS are completely driven only by the action of natural factors without any external energy power. Therefore, the improved design of PRHRS can actually eliminate the risk of severe accident and lays the necessary technical foundation for the faster and larger-scale development of PWR.
机译:加压水反应器(PWR)的核心残留散热系统是一种重要的设施,以确保反应器安全性,并且关闭后的故障将不可避免地导致核心的崩溃。然而,CPR1000的现有核心剩余散热系统仅保证72小时的宽限期,之后核心衰变热量仍然可以在一天内熔化核心。本研究提出了一种改进的无源残余散热系统(PRHRS)设计,其利用自然力来实现被动自动启动。同时,还提出了一种创新的方法来利用本文的最终散热器的气氛。随后进行了一个数值研究以验证事故条件期间改进设计的性能。数值结果表明,在驻地停电(SBO)场景中,PRHRS的改进设计保持了永恒的安全冷却能力。最后,进行参数敏感性研究以研究烟囱高度的合理设计价值。数值结果证明,即使大气温度是可变的,所提出的PRHR也能够连续去除核心残余热量。新设计的PRHR的所有组件功能仅通过自然因素的作用完全驱动,而无需任何外部能量。因此,PRHRS的改进设计实际上可以消除严重事故的风险,并为PWR的更快和更大的尺度发展奠定了必要的技术基础。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2021年第4期|111087.1-111087.10|共10页
  • 作者单位

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China|Wuhan Second Ship Design & Res Inst Wuhan 430064 Peoples R China;

    Wuhan Second Ship Design & Res Inst Wuhan 430064 Peoples R China;

    Wuhan Second Ship Design & Res Inst Wuhan 430064 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Improved design; Sensitivity study; Air cooling; Station blackout (SBO);

    机译:改进设计;敏感性研究;空气冷却;站停电(SBO);

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