燃料包壳破损条件下棒束间距对外逸气泡影响的可视化实验研究

Visual Experimental Study of Influence of Fuel Rod Bundle Spacing on Fission Gas Release under Fuel Cladding Failure Conditions

  • 摘要: 压水堆燃料包壳破损时释放出裂变气体,其产生的外逸气泡会影响子通道内的流动和传热特性,从而影响核反应堆的安全运行。为探究燃料棒的排布间距对外逸气泡行为的影响规律,本研究采用折射率匹配技术和高速摄像机,对外逸气泡在不同棒束间距的上升过程进行了3×3棒束排列的可视化实验研究。研究发现:棒束间距d=14.6 mm时,右侧外逸气泡的角波数最大,水平振幅最小;随着棒束间距d的增大,右侧外逸气泡平均水平偏移量增大,角波数减小;d=14.6~16.6 mm范围内外逸气泡的速度有较大的增幅,约为4.90%~7.48%;前侧外逸气泡较右侧外逸气泡更扁平,气泡倾斜角的变化与水平偏移量的变化呈正相关。现有的阻力系数预测模型并不适用于本实验的外逸气泡,因此提出了符合本实验所有工况的棒束间距与气泡等效直径之比、惯性力和表面张力的阻力预测公式,其预测值和实验值的相对误差都小于20%。

     

    Abstract: The release of fission gases from damaged cladding of pressurized water reactor fuel rods can significantly affect the flow and heat transfer characteristics in sub-channel. The presence of these escaping bubbles can lead to increase of localized temperature in the sub-channel, while high-velocity bubbles may cause deformation of the fuel rods, thereby impacting the safe operation of the nuclear reactor. Current research primarily focuses on fluid flow patterns, neglecting the influence of rod bundle spacing on bubble behavior within the sub-channel. To investigate the effect of fuel rod spacing on the behavior of escaping bubbles, this study employs refractive index matching techniques to eliminate optical errors caused by the rod bundles and utilizes high-speed photography to visualize the escaping bubbles rising at different rod bundle spacings. A 3×3 rod bundle arrangement was adopted with five sets of rod bundle spacings (d=12.6, 14.6, 16.6, 18.6, 20.6 mm). The results show that stable bubbles exhibit a zigzag ascent trajectory, which can be quantitatively represented using trigonometric functions. The mean squared error (MSE) of the fitting function for the rising trajectory increases with the rod bundle spacing. At a spacing of d=14.6 mm, the right-side escaping bubbles have the highest angular wave number and the lowest horizontal amplitude. As the rod bundle spacing d increases, the average horizontal displacement of the right-side escaping bubbles increases while the angular wave number decreases. Conversely, the front-side escaping bubbles do not follow this trend and tend to rise almost vertically. The velocity of escaping bubbles within the range of rod spacing d=14.6-16.6 mm increases significantly, ranging from 4.90% to 7.48%. This not only ensures the compactness of the fuel assembly, but also releases fission gases more quickly, improving the efficiency of safe operation of pressurized water reactors. Escaping bubbles maintain an elliptical shape during rising, with an aspect ratio consistently less than 1. The front-side escaping bubbles are flatter than those on the right side. The right-side escaping bubbles have an average aspect ratio of approximately 0.66-0.85, an average We of about 0.12-0.23, and an average Eo of around 14-20. The front-side escaping bubbles have an average aspect ratio of approximately 0.59-0.88, an average We of about 0.10-0.22, and an average Eo of around 13-26. The variation in bubble tilt angle was positively correlated with the change in horizontal displacement. As the horizontal displacement increases, the tilt angle also increases. Traditional drag prediction models have not effectively predicted the drag coefficient under the experimental conditions of this study. Therefore, this paper proposes a drag prediction equation based on the ratio of rod bundle spacing to the equivalent diameter of the bubbles, as well as the inertial and surface tension forces that are valid for all experimental conditions. Validation shows that the discrepancies between the predicted and experimental values are all less than 20%.

     

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