After the 2011 Fukushima accident, engineers of nuclear power plants are looking beyond the basic design requirements and ensuring that countermeasures are built in to avert possible nuclear accidents. In seismic probabilistic risk assessment (SPRA), uncertainties can be classified in two ways as aleatory uncertainties or epistemic uncertainties. To improve the reliability of SPRA, the difference in seismic response due to difference of building modelings related to epistemic uncertainty was focused on. Two modeling methods were used for a seismic response analysis: a three-dimensional finite-element model and a conventional sway-rocking stick model. Simulated input ground motions related to aleatory uncertainty were generated for the input waves. Then, the seismic floor response results of the various input ground motions of the two modeling methods were quantified. For the uncertainty quantification related to the different building modelings, a statistical analysis of the floor response results of the nuclear reactor building were further performed. Finally, for the quantification of the uncertainty in the fragility analysis for SPRA, the way to use of these results were discussed.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5144-9
PROCEEDINGS PAPER
Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building
Byunghyun Choi,
Byunghyun Choi
Japan Atomic Energy Agency, Kashiwa, Japan
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Akemi Nishida,
Akemi Nishida
Japan Atomic Energy Agency, Kashiwa, Japan
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Yinsheng Li,
Yinsheng Li
Japan Atomic Energy Agency, Kashiwa, Japan
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Ken Muramatsu,
Ken Muramatsu
Tokyo City University, Tokyo, Japan
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Tsuyoshi Takada
Tsuyoshi Takada
University of Tokyo, Tokyo, Japan
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Byunghyun Choi
Japan Atomic Energy Agency, Kashiwa, Japan
Akemi Nishida
Japan Atomic Energy Agency, Kashiwa, Japan
Yinsheng Li
Japan Atomic Energy Agency, Kashiwa, Japan
Ken Muramatsu
Tokyo City University, Tokyo, Japan
Tsuyoshi Takada
University of Tokyo, Tokyo, Japan
Paper No:
ICONE26-82034, V002T14A017; 9 pages
Published Online:
October 24, 2018
Citation
Choi, B, Nishida, A, Li, Y, Muramatsu, K, & Takada, T. "Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management. London, England. July 22–26, 2018. V002T14A017. ASME. https://doi.org/10.1115/ICONE26-82034
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