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Keywords: uncertainty quantification
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Proceedings Papers

Application of Polynomial Chaos Expansion in Uncertainty Quantification of Reactor Thermal-Hydraulic Calculation

Xiaoyu Zhang, Shubiao Dong, Wei Dong
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A028, August 8–12, 2022
Paper No: ICONE29-90403
https://doi.org/10.1115/ICONE29-90403
... Abstract In order to reduce the computational source required for uncertainty quantification of high-precision simulation program and make full use of mature commercial CFD software, the CFD model of coolant channels in the nuclear reactor is taken as the research object and the uncertainty...
View Paper titled, Application of Polynomial Chaos Expansion in <span class="search-highlight">Uncertainty</span> <span class="search-highlight">Quantification</span> of Reactor Thermal-Hydraulic Calculation
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Topics: Chaos, Polynomials, Uncertainty quantification
Proceedings Papers

Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT

Seokbin Seo, Nicholas R. Brown, Robert J. Armstrong, Charles P. Folsom, Colby B. Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A053, August 4–5, 2020
Paper No: ICONE2020-16884
https://doi.org/10.1115/ICONE2020-16884
... of the CHF on the sensitivity of input was found. RIA TREAT uncertainty quantification Sobol sensitivity analysis OPTIMIZATION STUDY FOR UNCERTAINTY REDUCTION OF IN-PILE CHF EXPERIMENTS IN TREAT Seokbin Seo1, Nicholas R. Brown1* 1University of Tennessee, Knoxville, TN Robert J. Armstrong2...
View Paper titled, Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT
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Topics: Critical heat flux, Optimization, Sensitivity analysis, Uncertainty, Coolants, Heat transfer, Transients (Dynamics), Accidents, Fuels, Heat flux
Proceedings Papers

Uncertainty Quantification of Seismic Response of Reactor Building Considering Different Modeling Methods

Byunghyun Choi, Akemi Nishida, Ken Muramatsu, Tatsuya Itoi, Tsuyoshi Takada
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A032, August 4–5, 2020
Paper No: ICONE2020-16862
https://doi.org/10.1115/ICONE2020-16862
... attention. Generally, an uncertainty quantification has been a very important undertaking to assess for fragility in NPP buildings. Therefore, this study focuses on the reduction in epistemic uncertainty by aiming to clarify the seismic-response effects on NPP buildings based on different modeling methods...
View Paper titled, <span class="search-highlight">Uncertainty</span> <span class="search-highlight">Quantification</span> of Seismic Response of Reactor Building Considering Different Modeling Methods
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Topics: Modeling, Nuclear power stations, Uncertainty quantification