A Design by Analysis procedure has been developed to incorporate the results of thermal cracking analyses into the linear based design methods for reinforced concrete containment structures. Current practice employs linear based analyses and accounts for stress reduction due to thermal induced cracking on a section by section basis. Under thermal loading, in addition to a reduction of the section forces and moments for cracked sections, concrete cracking also reduces the structural stiffness and thus the constraint against thermal expansion or contraction for the whole structure, which in turn reduces the thermal induced stresses as compared to a linear (un-cracked) analysis. The design by analysis approach employs nonlinear thermal cracking analyses using detailed modeling of the complete structure. By comparing these stress distributions with those from a linear analysis of the same model, stress reduction factors can be developed for critical sections that also include global stress redistribution. These stress reduction factors can then be used to correct linear based thermal stresses in the design basis calculation for all load combinations that include thermal loads.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Nonlinear Analyses for Thermal Cracking in the Design of Concrete Structures
Randy J. James,
Randy J. James
Anatech Corp., San Diego, CA
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Ai-Shen Liu
Ai-Shen Liu
GE Hitachi Nuclear Energy, San Jose, CA
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Randy J. James
Anatech Corp., San Diego, CA
Ai-Shen Liu
GE Hitachi Nuclear Energy, San Jose, CA
Paper No:
ICONE17-75474, pp. 153-160; 8 pages
Published Online:
February 25, 2010
Citation
James, RJ, & Liu, A. "Nonlinear Analyses for Thermal Cracking in the Design of Concrete Structures." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 153-160. ASME. https://doi.org/10.1115/ICONE17-75474
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