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Seismically induced uplift effects on nuclear power plants. Part II:Demand on internal equipment

机译:地震引起的对核电站的隆升效应。第二部分:内部设备需求

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摘要

This work focuses on the dynamic response of nuclear power plant mechanical sub-systems (i.e., main cooling system, steam generators, emergency cooling injection tanks and piping) that are housed within the containment structure and are associated with power generation. More specifically, the numerical modeling procedure focuses on the internal R/C wall structural system used for supporting the mechanical equipment. Next, the complex grid of the mechanical components is modeled with shell finite elements. This internal equipment configuration is then excited by the ground motion numerically predicted in Part I οf this work by considering geometrically nonlinear soil-structure interaction effects. Following extensive parametric studies, the seismic demand imposed on the internal equipment is assessed on the basis of dynamic stress analysis of the critical components. Depending on frequency content of the incoming seismic motion, it is shown that abrupt uplift may take place. This is true even for moderate earthquake intensity, particularly when the containment structure rests on soft soils and the vertical component of ground motion is not negligible. This situation may produce peaks in the pipe elbow strains that could potentially affect serviceability, operation and under extreme conditions, the safety of the entire nuclear power plant.
机译:这项工作的重点是容纳在安全壳结构内并与发电相关的核电厂机械子系统(即主冷却系统,蒸汽发生器,应急冷却注入罐和管道)的动态响应。更具体地说,数值建模过程集中在用于支持机械设备的内部R / C墙结构系统上。接下来,用壳有限元对机械零件的复杂网格进行建模。然后,通过考虑几何非线性土-结构相互作用的影响,通过这项工作的第一部分数值预测的地面运动激发这种内部设备的配置。经过广泛的参数研究,根据关键部件的动态应力分析评估了对内部设备施加的地震需求。根据传入地震运动的频率含量,表明可能发生突然隆升。即使对于中等地震强度也是如此,尤其是在安全壳结构位于软土上且地面运动的垂直分量不可忽略的情况下。这种情况可能会在管道弯头应变中产生峰值,这可能会影响整个核电站的可使用性,运行以及在极端条件下的安全性。

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