During recent years, power-uprate projects have been executed at several BWR-units in Sweden. As part of these projects, structural verification of the safety-related buildings as well as the new and old internal parts of the reactor pressure vessel, RPV, has been performed. In this document, some experiences will be presented from structural dynamic verification, using finite element analysis, FEA, within the scope of these power uprate projects. From this work, a number of conclusions can be drawn. Global models with dense meshes can successfully be used for a broad range of applications. Today, large FEA-models can be used efficiently, e.g. in global vibration and structural verification analyses, if suitable dynamic analysis methods are used. There can be strong dynamic interactions between the containment, fluids, the RPV and RPV-internals. Stress calculation and evaluation can be executed efficiently on large models. The structural models can with advantage be re-utilized in future projects.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4933-0
PROCEEDINGS PAPER
Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA
Bjo¨rn Sva¨rd,
Bjo¨rn Sva¨rd
Scanscot Technology AB, Lund, Sweden
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Jan-Anders Larsson,
Jan-Anders Larsson
Scanscot Technology AB, Lund, Sweden
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Philip Ma˚rtensson,
Philip Ma˚rtensson
Scanscot Technology AB, Lund, Sweden
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Bjo¨rn Lundin
Bjo¨rn Lundin
Scanscot Technology AB, Lund, Sweden
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Bjo¨rn Sva¨rd
Scanscot Technology AB, Lund, Sweden
Jan-Anders Larsson
Scanscot Technology AB, Lund, Sweden
Philip Ma˚rtensson
Scanscot Technology AB, Lund, Sweden
Bjo¨rn Lundin
Scanscot Technology AB, Lund, Sweden
Paper No:
ICONE18-30189, pp. 671-677; 7 pages
Published Online:
April 8, 2011
Citation
Sva¨rd, B, Larsson, J, Ma˚rtensson, P, & Lundin, B. "Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 671-677. ASME. https://doi.org/10.1115/ICONE18-30189
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