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Condensation in Horizontal Heat Exchanger Tubes

机译:水平热交换器管中的凝结

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Abstract: Many innovative reactor concepts for Generation Ⅲ nuclear power plants use passive safety equipment for residual heat removal. These systems use two phase natural circulation. Heat transfer to the coolant results in a density difference providing the driving head for the required mass flow. By balancing the pressure drop the system finds its operational mode. Therefore the systems depend on a strong link between heat transfer and pressure drop determining the mass flow through the system. In order to be able to analyze these kind of systems with the help of state of the art computer codes the implemented numerical models for heat transfer, pressure drop or two phase flow structure must be able to predict the system performance in a wide parameter range. Goal of the program is to optimize the numerical models and therefore the performance of computer codes analyzing passive systems. Within the project the heat transfer capacity of a heat exchanger tube will be investigated. Therefore the tube will be equipped with detectors, both temperature and pressure, in several directions perpendicular to the tube axis to be able to resolve the angular heat transfer. In parallel the flow structure of a two phase flow inside and along the tube will be detected with the help ofx-ray tomography. The water cooling outside of the tube will be realized by forced convection. It will be possible to combine the flow structure measurement with an angular resolved heat transfer for a wide parameter range. The test rig is set up at the TOPLFOW facility at the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), so that it will be possible to vary the pressure between 5 and 70 bar. The steam mass content will be varied between 0 and 100 percent. The results will be compared to the large scaled Emergency Condenser Tests performed at the INKA test facility in Karlstein (Germany). The paper will explain the test setup and the status of the project will be presented.
机译:摘要:Ⅲ代核电厂的许多创新反应堆概念使用被动安全设备进行剩余散热。这些系统使用两相自然循环。传热到冷却剂导致密度差,为所需的质量流量提供驱动头。通过平衡压力下降,系统找到其操作模式。因此,系统取决于传热和压力下降之间的强连接,从而确定通过系统的质量流量。为了能够在现有技术的状态下分析这些系统,用于传热,压降或两个相流结构的实现的数字模型必须能够在宽的参数范围内预测系统性能。该计划的目标是优化数值模型,从而优化计算机代码分析被动系统的性能。在该项目中,将研究热交换器管的传热容量。因此,管将配备有探测器,温度和压力,垂直于管轴的几个方向,以能够解析角传热。在并行中,将在射线断层扫描的帮助下检测内部和沿管内部和沿着管的流动结构。通过强制对流实现管外部的水冷却。可以将流动结构测量与用于宽参数范围的角度分辨的传热结合起来。测试钻机在Helmholtz-Zentrum Dresden-Rossendorf(HZDR)的Toplfow设施上设置,以便可以在5到70巴之间的压力变化。蒸汽质量含量在0到100%之间变化。结果将与在Karlstein(德国)的Inka测试设施中进行的大规模应急冷凝器试验进行比较。本文将解释测试设置,将呈现项目的状态。

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