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Numerical simulation of liquid fall induced gas entrainment and its mitigation

机译:液体降落引起的气体夹带的数值模拟及其缓解措施。

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摘要

In a number of chemical and nuclear engineering applications, a cover gas is maintained above a liquid pool. In a fast breeder reactor (FBR), argon gas is maintained above the sodium pools to ensure no direct contact between air and liquid sodium. Nevertheless, argon entrains into sodium by a variety of mechanisms, which is detrimental to the reactivity of the core. Furthermore, a large number of components that remain partially submerged in the liquid pool, aid in this undesirable gas entrainment process. The present study numerically explores liquid fall induced gas entrainment in an FBR hot pool. A passive strategy to mitigate gas entrainment is suggested in the form of a circumferential baffle plate. An optimal design for the baffle is achieved through systematic Computational Fluid Dynamic (CFD) simulations.
机译:在许多化学和核工程应用中,覆盖气体保持在液池上方。在快速增殖反应堆(FBR)中,氩气保持在钠池上方,以确保空气和液态钠之间不直接接触。然而,氩气通过多种机制夹带到钠中,这对核的反应性有害。此外,大量部分保留在液池中的组分有助于这种不希望的气体夹带过程。本研究从数值上探讨了FBR热水池中的液体掉落引起的气体夹带。建议采用一种被动的策略来减轻气体的夹带,其形式为周向挡板。挡板的最佳设计是通过系统的计算流体动力学(CFD)仿真来实现的。

著录项

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  • 作者单位

    Thermal Hydraulics Section. Nuclear and Safety Engineering Croup, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;

    Thermal Hydraulics Section. Nuclear and Safety Engineering Croup, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;

    Fluid Mechanics Laboratory, Department of Applied Mechanics, HT-Madras, Chennai 600 036, India;

    Thermal Hydraulics Section. Nuclear and Safety Engineering Croup, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India;

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

    CFD; VOF method; FBR; nuclear reactor; thermal-hydraulics; gas entrainment;

    机译:差价合约VOF法;FBR;核反应堆;热工液压;气体夹带;

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