TY - GEN
T1 - Modeling and Assessment for the Estimation of Heat Transfer Coefficients on Curved Downwards-Facing Heated Walls in Application to ERVC
AU - Osman, Sameer
AU - Afgan, Imran
AU - Addad, Yacine
N1 - Publisher Copyright:
© 2024 by ASME.
PY - 2024
Y1 - 2024
N2 - External Reactor Vessel Cooling (ERVC) is a proposed technique for severe accident mitigation in nuclear power plants. ERVC is aimed at containing the molten corium inside the Reactor Pressure Vessel (RPV) by transporting heat through the coolant (water) which occupies the intentionally flooded reactor cavity and is in direct contact with the outer surface of the lower head. An experimental study along with a computational fluid dynamics (CFD) model are used in the present study to investigate the local convection heat transfer coefficient on curved heated upper walls during the early stages of this type of severe accidents. The CFD study is realized using the open-source code OpenFOAM, in which proper formulation of the physics in terms of mass, momentum, and energy conservation is implemented. Results from the CFD model are compared to the experimental data obtained from a flow-boiling test facility, commissioned, and operated at Khalifa University, in the single-phase regime. The experimental findings highlight that the flat plate correlations are inaccurate for the estimation of the heat transfer coefficient on RPV lower head, especially at high Reynolds number values. Furthermore, the fully resolved turbulence model k-omega SST is the most accurate in predicting the actual thermal boundary layer and turbulent mixing. Quantification of the uncertainty in the experimental measurements as well as the discretization error in the numerical results is provided. In addition, a sensitivity analysis is provided for the inlet turbulence conditions to highlight their importance for accurate solutions. This study provides a framework for the assessment and validation of CFD codes dealing with heat transfer in scenarios where the flow is affected by curved geometries and fluid properties’ variations. In addition, it paves the way for more accurate heat transfer correlations suitable for heat flux partitioning models that can accurately capture the boiling curve in ERVC systems.
AB - External Reactor Vessel Cooling (ERVC) is a proposed technique for severe accident mitigation in nuclear power plants. ERVC is aimed at containing the molten corium inside the Reactor Pressure Vessel (RPV) by transporting heat through the coolant (water) which occupies the intentionally flooded reactor cavity and is in direct contact with the outer surface of the lower head. An experimental study along with a computational fluid dynamics (CFD) model are used in the present study to investigate the local convection heat transfer coefficient on curved heated upper walls during the early stages of this type of severe accidents. The CFD study is realized using the open-source code OpenFOAM, in which proper formulation of the physics in terms of mass, momentum, and energy conservation is implemented. Results from the CFD model are compared to the experimental data obtained from a flow-boiling test facility, commissioned, and operated at Khalifa University, in the single-phase regime. The experimental findings highlight that the flat plate correlations are inaccurate for the estimation of the heat transfer coefficient on RPV lower head, especially at high Reynolds number values. Furthermore, the fully resolved turbulence model k-omega SST is the most accurate in predicting the actual thermal boundary layer and turbulent mixing. Quantification of the uncertainty in the experimental measurements as well as the discretization error in the numerical results is provided. In addition, a sensitivity analysis is provided for the inlet turbulence conditions to highlight their importance for accurate solutions. This study provides a framework for the assessment and validation of CFD codes dealing with heat transfer in scenarios where the flow is affected by curved geometries and fluid properties’ variations. In addition, it paves the way for more accurate heat transfer correlations suitable for heat flux partitioning models that can accurately capture the boiling curve in ERVC systems.
KW - CFD
KW - ERVC
KW - Heat Transfer
KW - Nuclear Thermal Hydraulics
KW - Turbulence Modeling
UR - https://www.scopus.com/pages/publications/85197703450
U2 - 10.1115/VVUQ2024-132689
DO - 10.1115/VVUQ2024-132689
M3 - Conference contribution
AN - SCOPUS:85197703450
T3 - Proceedings of 2024 Verification, Validation, and Uncertainty Quantification Symposium, VVUQ 2024
BT - Proceedings of 2024 Verification, Validation, and Uncertainty Quantification Symposium, VVUQ 2024
T2 - 2024 Verification, Validation, and Uncertainty Quantification Symposium, VVUQ 2024
Y2 - 15 May 2024 through 17 May 2024
ER -