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Experimental and numerical investigation of the flow measurement method utilized in the steam generator of HTR-PM

机译:HTR-PM蒸汽发生器流量测量方法的实验与数值研究

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摘要

The helium flow measurement method is very important for the design of HTR-PM. Water experiments and numerical simulation with a 1/5 scaled model are conducted to investigate the flow measurement method utilized in the steam generator of HTR-PM. Pressure information at specific location of the 90 elbows with the diameter of 46.75 mm and radius ratio of 1.5 is measured to evaluate the flow rate in the riser-pipes. Pressure uniformity at the bottom of the experimental apparatus is tested to evaluate the influence of the equipment error on the final experimental results. Numerical results obtained by using the realizable kappa-8 model are compared with the experimental data. The results reveal that flow oscillation does not occur in the confluence system. For every single riser-pipe, the flow is stable despite the nonuniformity of the flow distribution. The average flow rates of the two pipe series show good repeatability regardless of the increases and decreases of the average velocity. In the header box, the flows out of the riser-pipes encounter with each other and finally distort the pressure distribution and the nonuniformity of the flow distribution becomes more significant along with the increasing Reynolds number. (C) 2016 Elsevier B.V. All rights reserved.
机译:氦流量测量方法对于HTR-PM的设计非常重要。进行了水实验和1/5比例模型的数值模拟,以研究HTR-PM蒸汽发生器中使用的流量测量方法。测量90个弯头的特定位置的压力信息,直径为46.75 mm,半径比为1.5,以评估立管中的流量。测试了实验设备底部的压力均匀性,以评估设备误差对最终实验结果的影响。使用可实现的kappa-8模型获得的数值结果与实验数据进行了比较。结果表明,在汇合系统中不会发生流动振荡。对于每根立管,尽管流量分布不均匀,流量仍然稳定。无论平均速度的增减,两个管道系列的平均流速均显示出良好的可重复性。在集管箱中,从立管流出的流彼此相遇,最终使压力分布变形,并且随着雷诺数的增加,流分布的不均匀性变得更加明显。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第8期|191-199|共9页
  • 作者单位

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

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

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

    Tsinghua Univ, Collaborat Innovat Ctr Adv Nucl Energy Technol, Inst Nucl & New Energy Technol, Key Lab Adv Reactor Engn & Safety,Minist Educ, Beijing 100084, Peoples R China|RMIT Univ, Sch Aerosp Mech & Mfg Engn, Melbourne, Vic 3083, Australia;

    Tsinghua Univ, Collaborat Innovat Ctr Adv Nucl Energy Technol, Inst Nucl & New 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
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  • 入库时间 2022-08-18 00:41:54

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