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Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor

机译:铅基反应堆堆芯出口温度波动的数值研究

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摘要

The temperature fluctuations induced by incomplete mixing of coolants with different temperature may cause thermal fatigue at the components of the lead-based reactor core outlet. Thus the accurate analysis of the phenomenon is very crucial for reactor safety operation. In this paper, the temperature fluctuations of the lead-based reactor core outlet were simulated by using large eddy simulation (LES) method in the simplified core outlet models. In order to analyze the temperature fluctuation sensitivity for the fuel assembly design parameters, such as the fuel assembly size and the gap between two adjacent fuel assemblies, five geometry models were constructed with different fuel assembly design parameters. The time histories of temperature fluctuations at different monitoring points on the center of three fuel assemblies were obtained. Then the amplitudes and the power spectrum density (PSD) of temperature fluctuations were analyzed, in order to compare temperature fluctuations of different geometry models at the same locations of core outlet. Finally the distribution characteristics of core outlet temperature fluctuations were obtained in axial directions, and the temperature fluctuation sensitivity with fuel assembly parameters was also analyzed based on the amplitudes, PSD and the normalized root-mean square temperature analysis. It is found that the temperature fluctuation intensity is enhanced with the increase of the gap size between adjacent fuel assemblies and the opposite edge width of each fuel assembly. The analysis results could provide important references for optimized design and engineering guidance of lead-based reactor. (C) 2018 Elsevier Ltd. All rights reserved.
机译:由温度不同的冷却剂不完全混合引起的温度波动可能会导致铅基反应堆堆芯出口组件的热疲劳。因此,对现象的准确分析对于反应堆安全运行至关重要。在简化的堆芯出口模型中,采用大涡模拟(LES)方法对铅基反应堆堆芯出口的温度波动进行了模拟。为了分析燃料组件设计参数(例如燃料组件尺寸和两个相邻燃料组件之间的间隙)的温度波动敏感性,构建了具有不同燃料组件设计参数的五个几何模型。得到了三个燃料组件中心不同监测点温度波动的时间历程。然后,分析温度波动的幅度和功率谱密度(PSD),以比较堆芯出口相同位置的不同几何模型的温度波动。最后,得出了堆芯出口温度波动的轴向分布特征,并基于振幅,PSD和归一化均方根温度分析,分析了带有燃料组件参数的温度波动敏感性。发现随着相邻燃料组件之间的间隙尺寸的增加以及每个燃料组件的相对边缘宽度的增加,温度波动强度增加。分析结果可为铅基反应器的优化设计和工程指导提供重要参考。 (C)2018 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2018年第7期|194-201|共8页
  • 作者单位

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

    Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Temperature fluctuation; Lead-based reactor; Core outlet;

    机译:温度波动;基于铅的电抗器;堆芯出口;

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