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Development and application of a mathematical model to design the venting system for corridors in nuclear power plants

机译:设计核电站走廊通风系统的数学模型的开发和应用

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摘要

When a lost of coolant accident (LOCA) takes place in a nuclear power plant (NPP), venting system should play the role of pressure relief and protecting civil structure. In current projects, engineers need the assist of computational fluid dynamic (CFD) simulations to design the venting system. However, CFD simulation consumes much time and computing resources, and much useless work exist before construction drawing design phase. Note that corridor is a kind of compartment widely exist in NPPs, a one dimensional mathematical model is developed to simplify the design of venting systems for corridors in this paper. Then CFD simulations are applied to validate the mathematical model, using the design of HTR-PM600's corridor as a typical case. Finally, a step-by-step flow of design is developed. From this study we know: 1) the mathematical model can indeed provide a preliminary design of the venting system for corridors, which is a reasonable approximation to that provided by CFD simulation; 2) engineers only need to follow 4 steps to use the mathematical model, much useless work is saved; 3) the mathematical model performs well in the design of HTR-PM600's corridor.
机译:当在核电厂(NPP)中发生冷却剂泄漏事故(LOCA)时,排气系统应起到泄压和保护民用结构的作用。在当前的项目中,工程师需要借助计算流体力学(CFD)模拟来设计通风系统。但是,CFD模拟会消耗大量时间和计算资源,并且在施工图设计阶段之前还存在许多无用的工作。请注意,走廊是核电厂中广泛存在的一种隔室,为简化走廊通风系统的设计,本文开发了一种一维数学模型。然后,以HTR-PM600走廊的设计为典型案例,通过CFD仿真来验证数学模型。最后,开发了逐步的设计流程。通过这项研究,我们知道:1)数学模型确实可以为走廊的通风系统提供初步设计,这是对CFD模拟所提供的方法的合理近似; 2)工程师只需遵循4个步骤即可使用数学模型,节省了大量无用的工作; 3)数学模型在HTR-PM600走廊的设计中表现良好。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2020年第1期|110369.1-110369.10|共10页
  • 作者

  • 作者单位

    Tsinghua Univ Inst Nucl & New Energy Technol Environm Technol Div Beijing 100084 Peoples R China;

    Tsinghua Univ Inst Nucl & New Energy Technol Div Reactor Phys Thermal Hydraul & Syst Simulat Beijing 100084 Peoples R China;

    Tsinghua Univ Inst Nucl & New Energy Technol Environm Technol Div Beijing 100084 Peoples R China|Tsinghua Univ Inst Nucl & New Energy Technol Collaborat Innovat Ctr Adv Nucl Energy Technol Key Lab Adv Reactor Engn & Safety Minist Educ Beijing 100084 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

    HTGR nuclear power plants; CFD; Venting system; Mathematical model; Corridor;

    机译:HTGR核电站;差价合约通风系统;数学模型;走廊;

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