Design Study on Skirt Support of Lead-Bismuth-Cooled Fast Reactor Vessel under Seismic Loading

Mei Huang; Juan Ma; J.N. Tang; Hao Yuan

doi:10.4028/www.scientific.net/AMM.385-386.304

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HomeApplied Mechanics and MaterialsApplied Mechanics and Materials Vols. 385-386Design Study on Skirt Support of...

Design Study on Skirt Support of Lead-Bismuth-Cooled Fast Reactor Vessel under Seismic Loading

Abstract:

This paper is aimed at analyzing the structural response of reactor vessel for Lead-Bismuth-Cooled fast reactor with cylindrical and conical shell skirt support respectively with a consideration of a fluid-structure interaction in the event of the earthquake. For a seismic design, three kinds of semi-conical apex angles for conical shell skirt support of vessel are analyzed and it is found the conical shell skirt support exhibits the better performance especially when semi-conical apex angle α=15°in the views of the stress intensity and stability.

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Periodical:

Applied Mechanics and Materials (Volumes 385-386)

Pages:

304-307

DOI:

https://doi.org/10.4028/www.scientific.net/AMM.385-386.304

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Online since:

August 2013

Authors:

Mei Huang, Juan Ma, J.N. Tang, Hao Yuan

Keywords:

Conical Shell Skirt Support, Lead-Bismuth-Cooled Fast Reactor, Seismic Analysis, Semi-Conical Apex Angle

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References

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