Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT

Xiaohan Zhao, Mingjun Wang, W. Tian, G. Su, S. Qiu
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Abstract

Steam Generator (SG) is a critical equipment in the nuclear power plant, it is the huge heat exchanger in reactor system which can achieve removing fission energy from the reactor system effectively to ensure safety of the whole nuclear system. It is located between the primary and the secondary loop in reactor system act as the intermediate hub of energy and the security barrier in nuclear power plant. Generally, there are numerous of U-shaped heat transfer tubes in SG it is one of the weakest structures throughout the primary loop system. So the integrity of the SG especially its heat transfer tubes is important to the safety of reactor operation. The degradation problem of heat transfer tubes together with ruptures accidents often occur under suffer environments in reactors, which include thermal stress, mechanical stress and so on, it is noteworthy that this kind of accidents is inevitable due to the limited properties of existing materials. The performance of the SG is seriously affected by the number of failure tubes. Plugging operations through various mechanical means is the most common method to solve the tubes ruptures problems which can reduce the economic losses to the utmost extent. However, plugging operations will make huge impact on the thermal hydraulic performances of both sides of SG. It’s meaningful to research the characteristics of the plugging affects under different operations. In this paper the hydraulic characteristics of primary side in AP1000 SG under a certain fraction of heat transfer tube plugging conditions is researched. Three dimensional hydraulic characteristics of primary side coolant in SG under different plugging conditions are obtained by using the thermal hydraulic software FLUENT. The typical plugging fraction in this simulation model is 10 percent, and the effect of plugging locations also be considered through changing the plugging positions using the zone marking method. The results shows that the pressure drop under the structure integrated SG is 358.01MPa which is accordance with the results from Westinghouse 343KPa. The pressure drop values varies when changing positions of the plugging tubes under the same plugging fraction condition. The flow fields in bottom head also change meanwhile and the maximum pressure drop can reach up to 388.05KPa when the plugging fraction is 10%. The growth rate become significant when tube plugging fraction larger than 5%, and differences between maximum and minimum values of total pressure drop under different plugging positions become larger gradually. Finally the local resistance coefficients and flow field distributions of primary side in SG under various plugging conditions are obtained which is meaningful for the reactor safety and it can be a good reference for the maintenance of SG.
利用FLUENT研究SG在堵管工况下的水力特性
蒸汽发生器是核电站的关键设备,它是反应堆系统中的大型热交换器,能有效地实现从反应堆系统中去除裂变能,保证整个核系统的安全。它位于反应堆系统一次回路和二次回路之间,是核电站的中间能量枢纽和安全屏障。一般来说,SG中存在大量的u型换热管,它是整个一次回路系统中最薄弱的结构之一。因此SG特别是传热管的完整性对反应堆的安全运行至关重要。在反应器的热应力、机械应力等恶劣环境下,传热管的退化问题和破裂事故经常发生,值得注意的是,由于现有材料的性能有限,这种事故是不可避免的。失效管的数量严重影响SG的性能。通过各种机械手段封堵是解决管柱破裂问题最常用的方法,可以最大限度地减少经济损失。然而,封堵作业将对SG两侧的热工性能产生巨大影响。研究不同工况下的堵漏影响特性具有重要意义。本文研究了在一定比例的换热管堵塞条件下,AP1000 SG机组一次侧水力特性。利用热工液压软件FLUENT,获得了SG一次侧冷剂在不同堵塞条件下的三维水力特性。该模拟模型的典型堵油率为10%,同时考虑了堵油位置的影响,采用区域标记法改变堵油位置。结果表明,结构集成SG下的压降为358.01MPa,与西屋343KPa的结果一致。在相同封堵分数条件下,封堵管位置不同,压降值也不同。同时,底部水头流场也发生了变化,当堵塞率为10%时,最大压降可达388.05KPa。当堵管分数大于5%时,总压降增长速度显著,不同堵管位置下总压降最大值与最小值的差异逐渐增大。最后得到了不同堵塞条件下SG内一次侧的局部阻力系数和流场分布,这对反应堆的安全性具有重要意义,也可为SG的维护提供良好的参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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