TY - GEN
T1 - Towards Uncertainty Quantification
T2 - 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025
AU - Abboud, Ali
AU - Garnier, Josselin
AU - Leturcq, Bertrand
AU - Lamorte, Nicolas
AU - de Lambert, Stanislas
N1 - Publisher Copyright:
© Proceedings of the 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025. All rights reserved.
PY - 2025/1/1
Y1 - 2025/1/1
N2 - In the core of nuclear reactors, fluid-structure interaction and intense irradiation lead to the progressive deformation of fuel assemblies. When this deformation becomes significant, it can result in additional costs and extended fuel unloading and reloading operations. Therefore, it is essential to develop effective fuel management strategies that minimize excessive deformation and interactions between fuel assemblies. However, accurately predicting deformation and the interactions that arise between fuel assemblies remains challenging due to the complex interdependencies of various phe-nomena, including neutronics, thermal-hydraulics, and thermomechanics, each subject to inherent uncertainties. This work presents a comprehensive approach to address these challenges by on the coupling between hydraulic and thermomechanical phenomena within a pressurized water reactor. An focusing initial sensitivity analysis was conducted to determine the most influential parameters, first in hydraulic models [A. Abboud et al., BEPU 2024, 272], and then in mechanical models [A. Abboud et al., M&C 2025, 46282]. To effectively manage uncertainties over several reactor power cycles, it is useful to have accurate surrogate models. Using this information, the coupled simulation aims to synergistically integrate hydraulic and mechanical effects, along with their interactions, to achieve a more accurate modeling of fuel assembly deformation while capturing the dependencies of each model to its uncertain parameters. Furthermore, this study goes beyond standard parameter uncertainties by addressing epistemic factors, such as the convergence algorithms and criteria used in the coupled simulations. By analyzing these coupled effects and the associated uncertainties, this work is intended to provide a deeper understanding of the interaction between hydraulic and me-chanical behaviors, enhancing the reliability and accuracy of predictive simulations. Ultimately, this integrated modeling approach will help to improve reactor management by informing more robust fuel management strategies and reducing risks related to fuel assembly deformation.
AB - In the core of nuclear reactors, fluid-structure interaction and intense irradiation lead to the progressive deformation of fuel assemblies. When this deformation becomes significant, it can result in additional costs and extended fuel unloading and reloading operations. Therefore, it is essential to develop effective fuel management strategies that minimize excessive deformation and interactions between fuel assemblies. However, accurately predicting deformation and the interactions that arise between fuel assemblies remains challenging due to the complex interdependencies of various phe-nomena, including neutronics, thermal-hydraulics, and thermomechanics, each subject to inherent uncertainties. This work presents a comprehensive approach to address these challenges by on the coupling between hydraulic and thermomechanical phenomena within a pressurized water reactor. An focusing initial sensitivity analysis was conducted to determine the most influential parameters, first in hydraulic models [A. Abboud et al., BEPU 2024, 272], and then in mechanical models [A. Abboud et al., M&C 2025, 46282]. To effectively manage uncertainties over several reactor power cycles, it is useful to have accurate surrogate models. Using this information, the coupled simulation aims to synergistically integrate hydraulic and mechanical effects, along with their interactions, to achieve a more accurate modeling of fuel assembly deformation while capturing the dependencies of each model to its uncertain parameters. Furthermore, this study goes beyond standard parameter uncertainties by addressing epistemic factors, such as the convergence algorithms and criteria used in the coupled simulations. By analyzing these coupled effects and the associated uncertainties, this work is intended to provide a deeper understanding of the interaction between hydraulic and me-chanical behaviors, enhancing the reliability and accuracy of predictive simulations. Ultimately, this integrated modeling approach will help to improve reactor management by informing more robust fuel management strategies and reducing risks related to fuel assembly deformation.
KW - Assembly bow
KW - Fluid-Structure Interaction
KW - Thermal Hydraulics
KW - Thermomechanics
KW - Uncertainty Quantification
UR - https://www.scopus.com/pages/publications/105022004637
U2 - 10.13182/PSA2025-46395
DO - 10.13182/PSA2025-46395
M3 - Conference contribution
AN - SCOPUS:105022004637
T3 - Proceedings of the 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025
SP - 942
EP - 951
BT - Proceedings of the 19th International Conference on Probabilistic Safety Assessment and Analysis, PSA 2025
PB - American Nuclear Society
Y2 - 15 June 2025 through 18 June 2025
ER -