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Test and Analysis Research on Seismic Structural Integrity of Nuclear Power Piping

机译:核电管道抗震结构完整性测试分析研究

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Current seismic design codes are very conservative in dealing with occasional seismic load for design of nuclear power piping system, which leads to application of large numbers of dampers, hangers and supports, and results in high cost for manufacture, installation, in-service inspection and repair of the nuclear power piping system. Based on current seismic design code and dynamic characteristics of piping system in nuclear power plant, three kinds of test specimens were tested for bearing vibrational or seismic limit loads, with both straight pipe and bend pipe tested on electromagnetic shake table and a typical large size 3D complex piping system tested in a 6m><6m seismic shake table. Leakage occurs in tests for straight pipes and bends, obvious plastic deformation remains in large size piping system. After the tests, finite element models for different tested specimens were made and results of nominal stress and cumulative fatigue factors were obtained with loads input originating from tests measurement data. Based on test and calculation results as well as relevant code items in RCC-M ,ASME and Chinese seismic design codes, it is suggested that damping ratio shall have a value of 5% for piping structure which has a frequency lower than 20Hz. It's also suggested that allowable stresses shall be remained unchanged while bending moments due to dynamic loads shall be reduced 50% in seismic analysis of piping system.
机译:当前的抗震设计规范在处理核电管道系统设计中的偶发地震载荷时非常保守,这导致应用大量的阻尼器,吊架和支撑架,并导致制造,安装,在役检查和维护的高成本。核电管道系统的维修。根据当前核电站的抗震设计规范和管道系统的动态特性,测试了三种试样的轴承振动或地震极限载荷,其中直管和弯管均在电磁振动台上进行了测试,典型的是大型3D复杂的管道系统在6m> 6m地震台上进行了测试。在直管和弯管的测试中会发生泄漏,在大型管道系统中仍会出现明显的塑性变形。测试后,针对不同的测试样本建立了有限元模型,并通过源自测试测量数据的载荷输入获得了标称应力和累积疲劳因子的结果。根据试验和计算结果以及RCC-M,ASME和中国抗震设计规范中的相关规范,建议对于频率低于20Hz的管道结构,阻尼比应为5%。还建议在管道系统的地震分析中,应将允许应力保持不变,同时将因动态载荷而引起的弯矩减小50%。

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