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Investigation of Design Criteria for Dynamic Loads on Nuclear Power Piping 核电管道动载荷设计准则的研究
为了证明超过ASME锅炉及压力容器规范允许动应力的重要性,进行了一项综合实验和分析程序。本报告的目的是介绍304 SS Schedule 40管道的试验工作,并评估有限元程序预测测量响应的能力。有限元分析和测量数据也与封闭形式的函数解进行了比较。研究结果表明,尽管超过了规范动态容许应力限值,但管道既没有损坏,也没有出现大塑性变形的迹象。
In order to demonstrate the significance of exceeding ASME Boiler and Pressure Vessel Code allowable dynamic stresses, a combined experimental and analytical program was conducted. The objective of the report is to present the experimental work on 304 SS Schedule 40 pipes and to evaluate the ability of finite element programs to predict measured responses. Finite element analyses and measured data are also compared to closed form functional solutions. Results of the study indicated that the piping neither damaged nor showed evidence of large plastic deformation although the code dynamic allowable stress limit is exceeded.
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