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首页> 外文期刊>International Journal of Heat and Mass Transfer >Experimental investigation on natural convection and thermal stratification of IRWST using PIV measurement
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Experimental investigation on natural convection and thermal stratification of IRWST using PIV measurement

机译：PIV法测量IRWST自然对流和热分层的实验研究

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摘要

Passive Residual Heat Removal Heat Exchanger (PRHR HX) immerged in the In-containment Refueling Water Storage Tank (IRWST) plays an important role in removing the core decay heat under non-Loss of Coolant Accident (LOCA) accident. In the initial stage of the Passive Residual Heat Removal System (PRHRS) activating, the natural convection is the main way to exchange heat between the secondary side of the PRHR HX with IRWST. However, it is almost impossible to acquire the thermohydraulic performance in IRWST since the influence of the natural convection and thermal stratification in IRWST happens simultaneously. In this paper, Hierarchical Two-Tiered Scaling (H2TS) method is employed to get scaling criteria based on control equations. Anda visualized water tank with five C-shape electrical heating tubes was scaled-down and applied to investigate the thermohydraulic performance for IRWST of CAP1400 Nuclear Power Plants (NPPs). Particle Image Velocimetry (PIV) measurement was used to investigate the evolution of the flow field of total twenty-five surfaces in three axial directions under three steady- and two variable-heating conditions. Meanwhile, three thermocouple bundles were adopted to acquire temperature data in three regions. The experimental results show that the temperature deviation in the same height of the IRWST is flattened by plenty of vortexes. As a result, local circulation and the temperature difference is less than 1 degrees C. While the thermal stratification along the vertical direction is obvious, the distribution of flow field and temperature demonstrate that a "dead zone" exists in bottom of the IRWST. Besides, a "thermal interface" region forms in the lower middle region as hot and cold fluid mixing. An obvious upwelling flow is observed near the PRHR HX heating rod bundle from flow fields of three axial directions. At the same time, the maximum height of the upwelling flow decreases with time increasing. On the one hand, the natural convection is induced by the thermal stratification. What is more, the thermal stratification will impair the scale and strength of natural convection, which will intensify the thermal stratification conversely. (C) 2019 Elsevier Ltd. All rights reserved.
机译：浸入控制内加油储水箱（IRWST）中的被动余热去除热交换器（PRHR HX）在去除非冷却剂事故（LOCA）事故下消除堆芯衰减热方面起着重要作用。在被动余热消除系统（PRHRS）激活的初始阶段，自然对流是PRHR HX次级侧与IRWST之间进行热交换的主要方式。但是，由于IRWST中自然对流和热分层的影响同时发生，因此在IRWST中几乎不可能获得热工水力性能。本文采用分层两层标度（H2TS）方法，基于控制方程获得标度准则。缩小了带有五个C形电加热管的可视化水箱，并将其应用于调查CAP1400核电站（NPP）的IRWST的热工水力性能。粒子图像测速（PIV）测量用于研究在三个稳态加热和两个可变加热条件下，总共25个表面在三个轴向上的流场的演变。同时，采用三个热电偶束采集三个区域的温度数据。实验结果表明，相同高度的IRWST的温度偏差被大量涡旋所抵消。结果，局部循环并且温度差小于1摄氏度。尽管沿垂直方向的热分层是明显的，但是流场和温度的分布表明在IRWST的底部存在“死区”。 。此外，当热流体和冷流体混合时，在下部中间区域形成“热界面”区域。在PRHR HX加热棒束附近，从三个轴向流场观察到明显的上升流。同时，上升流的最大高度随时间增加而减小。一方面，自然对流是由热分层引起的。此外，热分层会削弱自然对流的规模和强度，反之则会加剧热分层。 （C）2019 Elsevier Ltd.保留所有权利。

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  • 来源
  • 作者

    Du Weian; Liu Yusheng; Yuan Hongsheng; Qiao Shouxu; Tan Sichao;

  • 作者单位

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Minist Environm Protect, Nucl & Radiat Safety Ctr, Beijing 100084, Peoples R China;

    Nucl Power Inst China, Sci & Technol Rector Syst Design Technol Lab, Chengdu 610213, Sichuan, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

  • 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

    IRWST; PRHR HX; Natural convection; Thermal stratification; PIV measurement;

    机译：IRWST;PRHR HX;自然对流;热分层;PIV测量;

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