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Method for Elasto-plastic Seismic Time History Analysis of Piping System that imitate Internal Fluids as Acoustic Elements

机译:用于模拟内部流体作为声学元件的管道系统的弹塑性地震时间历史分析方法

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After the Great East Japan Earthquake in 2011, the necessity of reassess seismic safety of nuclear power plants components and system has emerged reconsidered worldwide. For reassessment, leading countries in nuclear power plant-related technologies, such as Japan and the United States, are developing new evaluation criteria based on current safety assessment techniques. Until now, operating nuclear power plants are designed through stress-based safety criteria which is differently applied by system and components according to specific safety design level. However, stress-based evaluation does not account for problems such as low cycle fatigue because it does not consider plastic deformation due to cyclic loading of earthquakes. To complement this, many studies including strain-based evaluation criteria have been published in Japan's JSME and United States' ASME. In order to confirm the evaluation criteria, an analytical model capable of simulating elastoplastic behavior by finite element model is required. Particularly, when building finite element analysis model for piping, it is essential to discuss the effects of internal fluids. In this study, we have studied how to properly simulate the effects of internal fluids in simulating the elasto-plastic behavior of the nuclear power plant piping system.
机译:在2011年大东日本地震之后,在全球重新考虑的核电站成分和系统重新评估抗震安全性的必要性。为了重新评估,核电厂相关技术(如日本和美国)正在开发基于当前安全评估技术的新评估标准。到目前为止,经营核电站是通过基于应力的安全标准设计的,该安全标准根据具体的安全设计水平通过系统和部件不同地应用。然而,基于应力的评估不会考虑低循环疲劳等问题,因为它不会因地震循环负载而考虑塑性变形。为了补充这一点,许多研究包括基于菌株的评估标准,已在日本的JSME和美国的ASME中公布。为了确认评估标准,需要一种能够通过有限元模型模拟弹性塑料行为的分析模型。特别是,当建立管道的有限元分析模型时,必须讨论内部流体的影响。在这项研究中,我们研究了如何正确模拟内部流体在模拟核电厂管道系统的弹性塑料行为时的影响。

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