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Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels

机译:垂直向上/向下流动通道中超临界水热工水力行为的数值分析

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摘要

Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the international SCWR community. However, there is still a lack of understanding of the heat transfer behavior of supercritical fluids. In this paper, the numerical analysis is carried out to study the thermal-hydraulic behaviour in vertical sub-channels cooled by supercritical water. Remarkable differences in characteristics of secondary flow are found, especially in square lattice, between the upward flow and downward flow. The turbulence mixing across sub-channel gap for downward flow is much stronger than that for upward flow in wide lattice when the bulk temperature is lower than pseudo-critical point temperature. For downward flow, heat transfer deterioration phenomenon is suppressed with respect to the case of upward flow at the same conditions.
机译:对SCWR燃料组件中热工液压行为的研究已引起国际SCWR界的极大关注。然而,仍然缺乏对超临界流体的传热行为的理解。本文通过数值分析研究了超临界水冷却的垂直子通道的热工水力行为。发现二次流动特性在向上流动和向下流动之间存在显着差异,特别是在方格中。当整体温度低于伪临界点温度时,宽通道的向下流动的湍流混合比向上流动的湍流要强得多。对于向下流动,相对于在相同条件下向上流动的情况,抑制了传热恶化现象。

著录项

  • 来源
    《核技术(英文版)》 |2008年第3期|178-186|共9页
  • 作者单位

    School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China;

    School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China;

    School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China;

    School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China;

  • 收录信息 中国科学引文数据库(CSCD);
  • 原文格式 PDF
  • 正文语种 chi
  • 中图分类 传热理论及其计算;
  • 关键词

    Supercritical water reactor; CFD; Heat transfer;

    机译:超临界水反应堆;CFD;传热;
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