SPONTANEOUS WATER HAMMERS IN A STEAM LINE IN THE CASE OF COLD WATER INGRESS
SPONTANEOUS WATER HAMMERS IN A STEAM LINE IN THE CASE OF COLD WATER INGRESS
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DOI：
10.1615/multscientechn.v20.i3-4.30
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发表时间：
2008
影响因子：
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通讯作者：
H. Prasser;Gyorgy Ezsol;G. Baranyai;T. Sühnel
中科院分区：
文献类型：
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作者：
H. Prasser;Gyorgy Ezsol;G. Baranyai;T. Sühnel
一些讨论过的俄罗斯型压水堆VVER-440的事故场景，假设蒸汽发生器的二次侧，由于来自一次侧或给水系统的水而供水过量。这种情况可能发生，例如，在从一次侧泄漏到二次侧的情况下，以及在地震期间，可能导致水进入主蒸汽管道，从而可能导致冷凝引起的水锤。本文的工作就是对这一现象进行实验研究。为此，KFKI-AEKI Budapest的PMK-2测试设备（VVER-440/W213的整体热水力模型）被扩展为蒸汽管线模型，该模型配备了新型两相流仪表以及快速压力和应变传感器。Forschungszentrum Dresden Rossendorf开发的应用网格传感器可以可视化水锤过程中的瞬态流动部分。局部空隙探头检测沿管道传播的弹塞。应用的新型探头配有微热电偶，可以提供局部瞬时温度测量和相位检测。这样就可以评估水和蒸汽交界处的温度梯度。本文介绍了试验装置和新型仪器。提出并讨论了第一次试验的结果。这项工作是WAHALoads项目的一部分，该项目是在第五个欧盟框架计划中进行的。该项目的目的是改进对核电站设备和支撑结构的水锤和冲击波引起的负荷的预测。
Some of the accident scenarios discussed for the Russian type pressurized water reactors VVER-440 assume an overfeed of the secondary side of the steam generators by water coming either from the primary side or from the feedwater system. This may happen, for example, in the case of a leakage from the primary to the secondary side, as well as during earthquakes, and can lead to water ingress into the main steam lines, where condensation-induced water hammer may be the consequence. The present work was initiated to study this phenomenon experimentally. For this purpose, the PMK-2 test facility of KFKI-AEKI Budapest, an integral thermohydraulic model of a VVER-440/W213, was extended by a steam-line model, which is equipped with a novel two-phase flow instrumentation as well as fast pressure and strain-gauge transducers. The applied mesh sensor developed by Forschungszentrum Dresden Rossendorf allows a visualization of the transient flow section during the water hammers. Local void probes detect the propagation of slugs along the pipe. The applied new kind of probe is equipped with microthermocouples to provide local instantaneous temperature measurements along with phase detection. This allows assessing temperature gradients at the boundary between the water and steam. The paper describes the test facility and the new instrumentation. The results of the first tests are presented and discussed. The work is part of the WAHALoads project, which was performed within the fifth EU framework program. The objective of the project was to improve the prediction of loads on equipment and support structures of nuclear power plants that are caused by water hammers and shock waves.