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Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant

机译:基于地震服务条件的核电站蝶阀结构安全性分析

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摘要

The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements.
机译:用于控制一次冷却剂回路中的冷却水以防止核电站反应堆内沸腾的阀门的结构完整性必须能够承受地震或其他危险情况。在这项研究中,根据KEPIC MFA,使用有限元方法进行了数值分析,即根据200A蝶阀动态特性的刚性或柔性特性进行了静态和动态分析。为了验证模态分析的结果,还进行了实验振动测试,其中通过考虑原位实验数据变化的模型更新方法获得了经过验证的有限元模型。通过使用经过验证的有限元模型,KEPIC MFA规定的SSE条件下的等效静载荷产生了135 MPa的应力,该应力发生在阀杆和阀体的连接处。当我们使用具有2%阻尼比的设计响应谱的CQC方法时,会引起更大的183 MPa应力。这些值低于用于制造蝶阀的材料的允许强度,因此,其结构安全性符合KEPIC MFA的要求。

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