Under the combined accident thermal and seismic loadings, the structural response of the AP1000 Auxiliary and Shield Building (ASB) is numerically investigated. A nonlinear Finite Element Model (FEM) of the AP1000 ASB is developed, in which the rebar in the reinforced concrete is explicitly described and the nonlinear behavior of the concrete is considered. The numerical modeling method and material models used by the reinforced concrete are validated by the testing results published in the literature. The propagation of the thermal loading-induced concrete cracks along the wall thickness is studied. Furthermore, the effects of thermal cracks on the wall stiffness, the development of the thermal stress and the axial forces acting on the reinforcement are fully discussed. The impact of thermal concrete cracks on the design demand of the rebar is also investigated. It is worthy of being further studied how to incorporate the appropriate reduction factor caused by concrete cracks into the linear structural design.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings
J. Jennifer Zhang,
J. Jennifer Zhang
Westinghouse Electric Company, Cranberry Township, PA
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Lee J. Tunon-Sanjur
Lee J. Tunon-Sanjur
Westinghouse Electric Company, Cranberry Township, PA
Search for other works by this author on:
J. Jennifer Zhang
Westinghouse Electric Company, Cranberry Township, PA
Lee J. Tunon-Sanjur
Westinghouse Electric Company, Cranberry Township, PA
Paper No:
ICONE22-31263, V001T03A030; 11 pages
Published Online:
November 17, 2014
Citation
Zhang, JJ, & Tunon-Sanjur, LJ. "Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T03A030. ASME. https://doi.org/10.1115/ICONE22-31263
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