| KEYWORD |
Inverse uncertainty quantification of nuclear thermal-hydraulic codes for the safety analysis of nuclear power plants
Reference persons NICOLA PEDRONI
Research Groups Nemo
Description In the past few decades, there has been an increasing interest in the use of Best Estimate Plus Uncertainty (BEPU) methodologies for the safety analyses of Nuclear Power Plants (NPPs). However, when using Best-Estimate Thermal-Hydraulic (BE-TH) system codes (e.g., ATHLET, CATHARE, RELAP, SPACE, TRACE, etc) the issue is the identification of the uncertainties affecting the code results. These are due to the physical models implemented in the code and its inputs. The quantification of the latter is performed relying on available experimental data, within a data analysis framework called Inverse Uncertainty Quantification (IUQ). Probabilistic Bayesian analysis can be used for IUQ problem supported by surrogate models based, e.g., Polynomial Chaos Expansion (PCE), Kriging, etc., to reduce the computational burden.
Within this framework, the purpose of this thesis is to develop innovative methods to advance IUQ methodologies. The thesis is performed within an international project called ATRIUM (Application Tests for Realization of Inverse Uncertainty quantification and validation Methodologies in thermal-hydraulics) launched by the Nuclear Energy Agency (NEA)/ Committee on the Safety of Nuclear Installations (CSNI)/ Working Group on the Analysis and Management of Accidents (WGAMA). The scope of the project is benchmarking the different IUQ methodologies with respect to physical phenomena relevant to intermediate break LOCA. (i.e., critical flow at the break and post-CHF heat transfer phenomena).
Option to be discussed: The methodologies will be possibly developed in collaboration between Politecnico di Torino, Politecnico di Milano and ENEA.
References
- Report NEA/CSNI/R(2016)9, “PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review”, 2016.
- Xu Wu, Ziyu Xie, Farah Alsafadi, Tomasz Kozlowski, “A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes”, Nuclear Engineering and Design 384 (2021) 111460.
- Giovanni Roma, Federico Antonello, Francesco Di Maio, Nicola Pedroni, Enrico Zio, Andrea Bersano, Cristina Bertani, Fulvio Mascari, “Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling”, Progress in Nuclear Energy 148 (2022) 104209.
- Giovanni Roma, Federico Antonello, Francesco Di Maio, Nicola Pedroni, Enrico Zio, Andrea Bersano, Cristina Bertani, Fulvio Mascari, “A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems “, Nuclear Engineering and Design 379 (2021) 111230.
- Nicola Pedroni, “Computational methods for the robust optimization of the design of a dynamic aerospace system in the presence of aleatory and epistemic uncertainties”, Mechanical Systems and Signal Processing (Special Issue NASA Langley Challenge on Optimization under Uncertainty), Volume 164, 1 February 2022, paper 108206.
See also tesi_inverse uncertainty quantification of thermal-hydraulic codes atrium - np - 3.pdf
Deadline 31/12/2025
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