首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >NUMERICAL SOLUTION OF HEAT TRANSFER PROCESS IN A PRISMATIC VHTR CONSIDERING CORE BYPASS AND CROSS FLOW
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NUMERICAL SOLUTION OF HEAT TRANSFER PROCESS IN A PRISMATIC VHTR CONSIDERING CORE BYPASS AND CROSS FLOW

机译:考虑核心绕过和横流的VHTR中传热过程的数值解

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The existence of interstitial gaps between fuel blocks in a VHTR are inevitable due to tolerances in manufacturing and installation, thermal expansion and irradiation shrinkage. Both bypass flow and cross flow gaps exist in the core. The coolant mass flow rate distribution, temperature distribution and hot spot are significantly affected by bypass and cross flow. In the present study, three-dimensional CFD analysis is conducted for the thermal analysis in the reactor core. Validation study for the turbulence model are performed by comparing the friction coefficient with published correlations. A sensitive study for near wall mesh is conducted to ensure the mesh quality. Parametric study by changing the size of bypass gap and cross gap are performed with a one-twelfth sector of fuel block. Simulation results show the influence of bypass gap size on temperature distribution and coolant mass flow rate distribution in the prismatic core. It is shown that the maximum fuel and coolant channel outlet temperature increases with the increase of gap size which may lead to a risk on the structure of fuel block. The cross flow is divided to two kinds. One is the cross flow from bypass gap to coolant channels and another is the flow from high pressure coolant channels to low pressure coolant channels. These two kinds of flow have opposite influence on temperature gradient. It is found that the presence of the cross flow gaps may have a significant effect on the distribution of the coolant in the core due to flow mixing in the cross gaps.
机译:由于制造和安装,热膨胀和辐照收缩的公差,VHTR中的燃料块之间不可避免存在间隙。堆芯中同时存在旁路流和错流缝隙。旁路和错流会显着影响冷却液的质量流量分布,温度分布和热点。在本研究中,对反应堆堆芯中的热分析进行了三维CFD分析。湍流模型的验证研究是通过将摩擦系数与已发表的相关性进行比较来进行的。对近壁网格进行了敏感研究,以确保网格质量。通过改变旁路间隙和交叉间隙的尺寸来进行参数研究,使用的是燃料块的十二分之一。仿真结果表明,旁路间隙尺寸对棱柱形芯中温度分布和冷却剂质量流量分布的影响。结果表明,最大的燃料和冷却液通道出口温度随着间隙尺寸的增加而增加,这可能会导致燃料块结构的风险。错流分为两种。一个是从旁通间隙到冷却剂通道的横流,另一个是从高压冷却剂通道到低压冷却剂通道的流。这两种流动对温度梯度有相反的影响。已经发现,由于交叉间隙中的流动混合,交叉流动间隙的存在可能对冷却剂在堆芯中的分布具有显着影响。

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