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Hydraulic design of primary sodium header of a fast spectrum reactor by computational and experimental studies

机译:通过计算和实验研究快速光谱反应器一次钠联管箱的水力设计

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摘要

Computational fluid dynamics (CFD) investigations of flow and pressure distributions in the primary sodium header of fast reactor have been carried out. The focus of the study is to quantify the magnitude of swirl superimposed on main flow and assess its influence on pressure loss in the header and flow maldistribution among the primary pipes. From compact layout considerations, a spherical shape has been chosen for the header. The static pressure loss coefficient for the basic 'header-primary pipe' assembly without any internals is determined to be 7.2. With suitable internal baffles and a central cone this value is reduced to 1.22. The loss coefficients predicted by CFD studies have been validated by conducting experiments on 1:3 scale air models. Following this, an integrated CFD study of header coupled with sodium pump including impeller and diffuser has been carried out It is seen that the diffuser induces a strong swirl in the fluid entering the header. Due to this swirl, the total pressure loss coefficient in the header-pipe assembly increases by a factor of two, when compared to that without the swirl. The swirl also leads to flow mal-distribution among the two primary pipes to the extent of ±9% from the mean value. This flow mal-distribution is an important input for safety analysis of the reactor for the event of 'one primary pipe rupture'.
机译:已对快堆主要钠集管中的流量和压力分布进行了计算流体力学(CFD)研究。该研究的重点是量化叠加在主流上的旋涡的大小,并评估其对集管中的压力损失和主要管道之间的流量分布不均的影响。从紧凑的布局考虑,已选择球头为球形。不带任何内部零件的基本“头部-主管道”组件的静压力损失系数确定为7.2。使用合适的内部挡板和中心锥,该值减小到1.22。通过CFD研究预测的损耗系数已通过在1:3比例的空气模型上进行实验而得到验证。此后,对集管与包括叶轮和扩散器的钠泵相结合的集管进行了综合CFD研究。可以看出,扩散器在进入集管的流体中引起强烈的涡流。由于该涡旋,与没有涡旋的总压力损失系数相比,总管总压力损失系数增加了两倍。旋流还会导致两个主管之间的流量分配不均,其平均值为±9%。对于“一次主管道破裂”事件,这种流量分配不均是反应堆安全分析的重要输入。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2013年第3期|117-129|共13页
  • 作者单位

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

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

    AU-FRG Institute for CAD/CAM, Anna University, Chennai 600 025, India;

    Fluid Control Research Institute, Palghat, Kerala, India;

  • 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

    fast reactor; computational fluid dynamics; air experiments; minimization of pressure loss; flow mal-distribution; swirl;

    机译:快速反应堆计算流体动力学;空中实验;压力损失最小化;流量分配不均;漩涡;
  • 入库时间 2022-08-18 00:43:32

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