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Flow instability analysis of supercritical water-cooled reactor CSR1000 based on frequency domain

机译:基于频域的超临界水冷堆CSR1000流动不稳定性分析

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摘要

Flow instability was studied for supercritical water-cooled reactor CSR1000 based on frequency domain method in this paper. A code named FREDO-CSR1000 (Frequency Domain Analysis of CSR1000) has been developed. The analysis of flow instability for CSR1000 both in average channel and hot channel within rated power and flow has been performed with the FREDO-CSR1000 code. The key parameters including decay ratio, the maximum cladding surface temperature and the proper orifice pressure drop coefficient were obtained as well. The calculation results indicated that the decay ratio of the first flow path varies with power and flow monotonically. However, the decay ratio of the second flow path ascends first and then descends, the trend of which is fluctuant because of the simultaneous influence of a multitude of variables. Besides, it is found that the location where the flow instability happened is directly determined by the point at which the pseudo-critical temperature reached. Moreover, the neutral stability boundary for hot channel of CSR1000 was obtained so that the threshold of flow instability can be predicted.
机译:本文基于频域法研究了超临界水冷堆CSR1000的流动不稳定性。已经开发了名为FREDO-CSR1000(CSR1000的频域分析)的代码。已使用FREDO-CSR1000代码对CSR1000在额定功率和流量范围内的平均通道和热通道中的流量不稳定性进行了分析。还获得了包括衰减比,最大包层表面温度和适当的孔口压降系数在内的关键参数。计算结果表明,第一流路的衰减率随功率和流量单调变化。然而,第二流动路径的衰减率先上升然后下降,由于多个变量的同时影响,其趋势是波动的。此外,发现流动不稳定发生的位置直接由达到伪临界温度的点确定。此外,获得了CSR1000热通道的中性稳定性边界,从而可以预测流动不稳定的阈值。

著录项

  • 来源
    《Annals of nuclear energy》 |2012年第2012期|p.70-80|共11页
  • 作者单位

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

    Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China Nuclear Power Institute of China, Cheng-du 6500, China;

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

    supercritical water-cooled reactor CSR1000; frequency domain; transfer function; flow instability; decay ratio;

    机译:超临界水冷堆CSR1000;频域转换功能;流量不稳定;衰减率;

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