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Particle image velocimetry measurements in a representative gas-cooled prismatic reactor core model for the estimation of bypass flow.

机译:在代表性的气冷棱柱形反应堆堆芯模型中的颗粒图像测速测量,用于估算旁路流量。

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摘要

Core bypass flow is considered one of the largest contributors to uncertainty in fuel temperature within the Modular High Temperature Gas-cooled Reactor (MHTGR). It refers to the coolant that navigates through the interstitial regions between the graphite fuel blocks instead of traveling through the designated coolant channels. These flows are of concern because they reduce the desired flow rates in the coolant channels, and thereby have significant influence on the maximum fuel element and coolant exit temperatures. Thus, accurate prediction of the bypass flow is important because it directly impacts core temperature, influencing the life and efficiency of the reactor. An experiment was conducted at Idaho National Laboratory to quantify the flow in the coolant channels in relation to the interstitial gaps between fuel blocks in a representative MHTGR core. Particle Image Velocimetry (PIV) was used to measure the flow fields within a simplified model, which comprised of a stacked junction of six partial fuel blocks with nine coolant tubes, separated by a 6mm gap width. The model had three sections: The upper plenum, upper block, and lower block. Model components were fabricated from clear, fused quartz where optical access was needed for the PIV measurements. Measurements were taken in three streamwise locations: in the upper plenum and in the midsection of the large and small fuel blocks. A laser light sheet was oriented parallel to the flow, while velocity fields were measured at millimeter intervals across the width of the model, totaling 3,276 PIV measurement locations. Inlet conditions were varied to incorporate laminar, transition, and turbulent flows in the coolant channels—all which produced laminar flow in the gap and non-uniform, turbulent flow in the upper plenum. The images were analyzed to create vector maps, and the data was exported for processing and compilation. The bypass flow was estimated by calculating the flow rates through the coolant channels and gap, then forming a ratio of the results. It was found that the gap consumed about 6.9-15.8% of the total flow for a channel Reynolds number between 1,700 and 4,600, where the flow distribution amid the coolant channels varied less than 4.6%.
机译:堆芯旁通流量被认为是模块化高温气冷堆(MHTGR)内燃料温度不确定性的最大因素之一。它是指通过石墨燃料块之间的间隙区域而不是通过指定的冷却剂通道行进的冷却剂。这些流量之所以令人关注,是因为它们降低了冷却液通道中的所需流量,从而对最大燃料元件和冷却液出口温度产生重大影响。因此,准确预测旁路流量非常重要,因为它会直接影响堆芯温度,从而影响反应堆的寿命和效率。在爱达荷州国家实验室进行了一项实验,以量化代表MHTGR堆芯中燃料块之间的间隙相对于冷却剂通道的流量。粒子图像测速(PIV)用于测量简化模型内的流场,该模型由六个局部燃料块与九个冷却剂管的堆叠结点组成,并以6mm的间隙宽度隔开。该模型分为三个部分:上气室,上块和下块。模型组件由透明的熔融石英制成,需要进行光学测量以进行PIV测量。在三个流向位置进行了测量:在大型燃料块和小型燃料块的上部气室和中部。激光片的方向平行于流,同时在整个模型宽度上以毫米间隔测量速度场,总共3276个PIV测量位置。入口条件有所变化,以在冷却剂通道中合并层流,过渡流和湍流-所有这些都会在间隙中产生层流,并在上增压室中产生不均匀的湍流。分析图像以创建矢量地图,并将数据导出以进行处理和编译。通过计算通过冷却液通道和间隙的流量,然后形成结果的比率,来估算旁路流量。已发现,在1700至4600之间的通道雷诺数中,间隙消耗的总流量约为6.9-15.8%,其中冷却剂通道之间的流量分布变化小于4.6%。

著录项

  • 作者

    Conder, Thomas E.;

  • 作者单位

    University of Idaho.;

  • 授予单位 University of Idaho.;
  • 学科 Engineering Mechanical.;Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2012
  • 页码 95 p.
  • 总页数 95
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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