Abstract
This paper describes the analysis and design of the common raft for a Chinese third-generation nuclear power plant. The configuration of the common raft and the key methodologies involving in its analysis and design were studied. The general finite element software ANSYS was used to build the finite element model of nuclear island buildings, apply the loads on the model, and finally obtain the stress distribution and therefore the reinforcement requirement. During the process, transient temperature analysis method was adopted to get the temperature distribution in the common raft when accident condition happened. Instead of quasistatic method, the time history analysis method was employed in the stability analysis of the common raft. The common raft design was optimized by using the advanced techniques mentioned above.
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References
Code for Seismic Design of Nuclear Power Plants GB50267-97.
Design Requirements for Prestressed Concrete Containment for Pressure Water Reactor Nuclear Power Plant NB/T 20303-2014.
Design Requirements for Nuclear Safety Related Concrete Structure for Pressure Water Reactor Nuclear Power Plant (NB/T20012-2010);
Design code for nuclear safety related plants foundation for pressure water reactor nuclear power plants(NB/T 20308-2014).
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© 2017 Springer Science+Business Media Singapore
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Xiaoying, S., Ran, S., Jian, M., Yulin, L. (2017). Analysis and Design of the Common Raft for a Chinese Third-Generation Nuclear Power Plant. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2314-9_1
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DOI: https://doi.org/10.1007/978-981-10-2314-9_1
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Publisher Name: Springer, Singapore
Print ISBN: 978-981-10-2313-2
Online ISBN: 978-981-10-2314-9
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