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3D CFD simulations to study the effect of inclination of condenser tube on natural convection and thermal stratification in a passive decay heat removal system

机译:3D CFD模拟,以研究冷凝器管的倾斜度对被动衰减排热系统中自然对流和热分层的影响

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摘要

Many advanced nuclear reactors adopt methodologies of passive safety systems based on natural forces such as gravity. In one of such system, the decay heat generated from a reactor is removed by isolation condenser (ICs) submerged in a large water pool called the Gravity Driven Water Pool (GDWP). The objective of the present study was to design an IC for the passive decay heat removal system (PDHRS) for advanced nuclear reactor. First, the effect of inclination of IC tube on three dimensional temperature and flow fields was investigated inside a pilot scale (10 L) GDWP. Further, the knowledge of these fields has been used for the quantification of heat transfer and thermal stratification phenomenon. In a next step, the knowledge gained from the pilot scale GDWP has been extended to design an IC for real size GDWP (similar to 10,000 m(3)). Single phase CFD simulation using open source CFD code [OpenFOAM-2.2] was performed for different tube inclination angles (alpha) (w.r.t. to vertical direction) in the range 0 degrees <= alpha <= 90 degrees. The results indicate that the heat transfer coefficient increases with increase in tube inclination angle. The heat transfer was found to be maximum for alpha = 90 degrees and minimum for alpha = 15 degrees. This behavior is due to the interaction between the primary flow (due to pressure gradient) and secondary flow (due to buoyancy force). The primary flow enhanced the fluid sliding motion at the tube top whereas the secondary flow resulted in enhancement in fluid motion along the circumference of tube. As the angle of inclination (alpha) of the tube was increased, the secondary flow became dominant and resulted into enhanced heat transfer near the tube bottom. Three different heat transfer regimes were identified in the transient period: conduction (0 < t < 0.4 s), quasi-steady (0.4 s < t < 10 s) and fluctuating period (10 s < t < 100 s). The effect of inclination angle (alpha) was more pronounced in the fluctuating period. The natural convection and heat transfer in the regime of laminar-turbulent transition was studied in the presence of longitudinal vortices. The heat transfer was enhanced in the transition region due to vortices formation and it was reduced in the turbulent regime due to decay of vortices. (C) 2016 Elsevier B.V. All rights reserved.
机译:许多先进的核反应堆都采用基于自然力(例如重力)的被动安全系统方法。在这样的系统之一中,由反应堆产生的衰减热通过浸没在称为重力驱动水池(GDWP)的大型水池中的隔离冷凝器(IC)去除。本研究的目的是设计一种用于先进核反应堆的被动衰变除热系统(PDHRS)的集成电路。首先,在中试规模(10升)GDWP内研究了IC管倾斜度对三维温度和流场的影响。此外,这些领域的知识已用于量化传热和热分层现象。下一步,从试点规模GDWP获得的知识已经扩展到设计用于实际尺寸GDWP(类似于10,000 m(3))的IC。使用开源CFD代码[OpenFOAM-2.2]进行单相CFD仿真,以在0度<= alpha <= 90度范围内的不同管倾斜角(相对于垂直方向为w.r.t.)进行。结果表明,传热系数随着管子倾角的增加而增加。发现热传递对于α= 90度最大,而对于α= 15度最小。此行为是由于主流(由于压力梯度)和次级流(由于浮力)之间的相互作用所致。一次流动增强了在管顶部的流体滑动运动,而二次流动导致了沿着管的圆周的流体运动增强。随着管的倾斜角(α)的增加,二次流占主导地位,并导致管底部附近的传热增强。在过渡期间确定了三种不同的传热方式:传导(0

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  • 来源
    《Nuclear Engineering and Design》 |2016年第8期|582-603|共22页
  • 作者单位

    Homi Bhabha Natl Inst, Bombay 400094, Maharashtra, India;

    Homi Bhabha Natl Inst, Bombay 400094, Maharashtra, India|Inst Chem Technol, Dept Chem Engn, Bombay 400019, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, 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

  • 入库时间 2022-08-18 00:41:49

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