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堆芯上腔室流动中SST k-ω湍流模型参数的不确定度量化

Uncertainty Quantification of SST k-ω Turbulence Model Parameters in the Upper Plenum Flow of Nuclear Reactors

  • 摘要: 铅基堆堆芯上腔室的温度振荡现象是影响核电站安全稳定运行的关键因素之一,其准确描述对热脉动机制的分析具有重要意义。采用SST k-ω湍流模型对该现象进行了数值模拟研究,定量分析了模型中β1β2β*三个参数对温度结果的影响及其不确定区间,并进行了参数敏感度分析。研究结果表明,温度不确定性的分布特征与流体流动和混合过程有着密切的联系。喷口附近区域由于受到喷口射流的直接影响,温度不确定性较低;而冷热喷口中间区域由于流体混合作用强烈,不确定性相对较高,特别地,在所研究的参数范围内,β2β*对温度结果不确定性的贡献较大。这些发现为后续模型改进和工程应用提供了科学指导。

     

    Abstract: The temperature oscillation phenomenon in the upper plenum of the reactor core is one of the key factors affecting the safe and stable operation of lead-based nuclear power plants, and its accurate description is of great significance for the analysis of thermal striping mechanisms. By employing the SST k-ω turbulence model for numerical simulation on this phenomenon, a quantitative analysis of the impact of the three parameters β1, β2, and β* in the model on the temperature results and their uncertainty intervals was conducted, along with a sensitivity analysis of the parameters. The research results indicate that the distribution characteristics of temperature uncertainty are closely related to fluid flow and mixing processes. The temperature uncertainty is relatively low in areas near the nozzles due to the direct impact of the jet, while it is relatively high in the intermediate areas between the cold and hot nozzles due to intense fluid mixing. In particular, the parameters β2 and β* have a significant contribution to the uncertainty of the temperature results within the studied range. These findings provide scientific guidance for subsequent model improvements and engineering applications.

     

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