Investigation of Design Criteria for Dynamic Loads on Nuclear Power Piping

Investigation of Design Criteria for Dynamic Loads on Nuclear Power Piping

Investigation of Design Criteria for Dynamic Loads on Nuclear Power Piping

Standard
Format: PDF
Published year: 1987
Organization: WRC
Language: English
Pages: 20
ISEN: WRC Bulletin 324

Summary

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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