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首页> 外文期刊>Nuclear Technology >THE THERMAL HYDRAULICS OF TUBE SUPPORT FOULING IN NUCLEAR STEAM GENERATORS
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THE THERMAL HYDRAULICS OF TUBE SUPPORT FOULING IN NUCLEAR STEAM GENERATORS

机译：核蒸汽发生器中管子支撑的热工水力

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摘要

It is hypothesized that the thermal-hydraulic environment plays a role in the fouling of tube supports in nuclear steam generators. Experiments were performed to simulate the thermal-hydraulic environment near various designs of supports. Pressure loss, local velocity, turbulence intensity, and local void fraction were measured to characterize the effect of the support. Fouling mechanisms specific to supports were inferred from these experimental data and from actual steam generator inspection results. An analytical model was developed to predict the rate of paniculate deposition on the supports, to better understand the complex processes involved. This paper presents the following set of tools for assessing the fouling propensity of a given support design: (1) proposed fouling mechanisms, (2) criteria for support fouling propensity, (3) correlation of fouling with parameters such as mass flux and quality, (4) descriptions of experimental tools such as flow visualization and measurement of pressure-loss profiles, and (5) analytical tools. An important conclusion from this and our previous work is that the fouling propensity is greater with broached support plates, both trefoil and quatrefoil, than with lattice bar supports and formed bar supports, in which significant cross flows occur.
机译：假设热液压环境在核蒸汽发生器中的管支架结垢中起作用。进行实验以模拟各种设计的支架附近的热工环境。测量压力损失，局部速度，湍流强度和局部空隙率以表征载体的作用。从这些实验数据和实际的蒸汽发生器检查结果可以推断出特定于载体的结垢机理。开发了一种分析模型来预测颗粒在载体上的沉积速率，以更好地理解所涉及的复杂过程。本文介绍了用于评估给定支撑设计的结垢倾向的以下工具：（1）提出的结垢机制；（2）支撑结垢倾向的标准；（3）结垢与质量通量和质量等参数的相关性； （4）实验工具的描述，例如流量可视化和压力损失曲线的测量，以及（5）分析工具。由此和我们先前的工作得出的重要结论是，带拉丝的支撑板（三叶形和四叶形）的结垢倾向要比格状杆支撑和成形杆支撑的结垢倾向大，后者会发生明显的错流。

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