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首页> 外文会议>International conference on nuclear engineering >DEVELOPMENT OF NUMERICAL SIMULATION FOR JET BREAKUP BEHAVIOR IN COMPLICATED STRUCTURE OF BWR LOWER PLENUM (2) FLOW OBSERVATION WITH VISUALIZED EXPERIMENTAL APPARATUS
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DEVELOPMENT OF NUMERICAL SIMULATION FOR JET BREAKUP BEHAVIOR IN COMPLICATED STRUCTURE OF BWR LOWER PLENUM (2) FLOW OBSERVATION WITH VISUALIZED EXPERIMENTAL APPARATUS

机译：可视化实验装置对BWR下腔室复杂结构射流破坏行为数值模拟的研究（2）流动观察

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In order to improve the safety of Boiling Water Reactor (BWR), it is required to know the behavior of the plant when an accident occurred as can be seen at Fukushima Daiichi nuclear power plant accident. Especially, it is important to estimate the behavior of molten core jet in the lower part of the containment vessel at severe accident. In the BWR lower plenum, the flow characteristics of molten core jet are affected by many complicated structures, such as control rod guide tubes (CRGT), instrument guide tubes and core support plate. However, it is difficult to evaluate these effects on molten core jet experimentally. Therefore, we considered that multi-phase computational fluid dynamics approach is the best way to estimate the effects on molten core jet by complicated structure. The objective of this study is to develop the evaluation method for the flow characteristic of molten core jet including the effects of the complicated structures in the lower plenum. So we are developing a simulation method to estimate the behavior of molten core jet falling down through the core support plate to the lower plenum of the BWR. The method has been developed based on interface tracking method code TPFIT (Two Phase Flow simulation code with Interface Tracking). To verify and validate the applicability of the developed method in detail, it is necessary to obtain the experimental data that can be compared with detailed numerical results by the TPFIT. Thus, in this study, we are carrying out experimental works by use of multi-phase flow visualization technique. For the experiment works, we constructed two experimental apparatuses, one is single-channel experimental apparatus and the other is multi-channel experimental apparatus. The single-channel experimental apparatus simply simulate single flow channel between four CRGTs. The multichannel experimental apparatus is a 1/10 planar type model of a lower plenum of BWR. In the experiments, we will obtain the jet breakup behavior and surrounding velocity profiles of the jet by using LIF and PIV. In this paper, the outline of two-experimental apparatuses are shown. And the results of the single-channel experimental apparatus with/without modelled complicated structures are also shown. In the results, it was confirmed that the complicated flow channel affects the jet injection and breakup behavior. And it was also confirmed that the complicated structures restrain diffusion of fragments of the jet.
机译：为了提高沸水反应堆（BWR）的安全性，需要了解事故发生时电厂的行为，如在福岛第一核电站事故中可以看到的那样。尤其重要的是，估计发生严重事故时在安全壳下部的熔芯射流的行为。在BWR下增压室中，熔融堆芯射流的流动特性受许多复杂结构的影响，例如控制杆导管（CRGT），仪器导管和堆芯支撑板。但是，很难通过实验评估这些对熔融岩心射流的影响。因此，我们认为多相计算流体动力学方法是估算复杂结构对熔融岩心射流影响的最佳方法。这项研究的目的是开发一种评估熔芯射流流动特性的方法，其中包括下增压室中复杂结构的影响。因此，我们正在开发一种模拟方法，以估算熔融岩心射流从岩心支撑板下落到BWR下部气室的行为。该方法是基于接口跟踪方法代码TPFIT（带有接口跟踪的两相流仿真代码）开发的。为了详细验证和验证所开发方法的适用性，有必要获得可以与TPFIT与详细数值结果进行比较的实验数据。因此，在这项研究中，我们正在使用多相流可视化技术进行实验工作。对于实验工作，我们构造了两个实验设备，一个是单通道实验设备，另一个是多通道实验设备。单通道实验设备仅模拟四个CRGT之间的单个流道。多通道实验装置是BWR下腔室的1/10平面型模型。在实验中，我们将通过使用LIF和PIV获得射流破裂行为和射流的周围速度分布。在本文中，显示了两个实验设备的概述。并显示了带有/不带有建模复杂结构的单通道实验设备的结果。结果证实，复杂的流动通道会影响射流的喷射和破裂行为。并且还证实了复杂的结构抑制了射流碎片的扩散。

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