TY - GEN
T1 - Wall-resolved LES and Low-Reynolds Number URANS combined to an Arbitrary Lagrangian Eulerian approach for Predicting Water Cross-Flow Induced vibrations of a Single Flexible Tube in a Normal Square Tube Array
AU - Benhamadouche, Sofiane
AU - Benguigui, William
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023/1/1
Y1 - 2023/1/1
N2 - In the context of nuclear engineering, Flow-Induced Vibration (FIV) in steam generators can lead to mechanical damage, responsible for safety issues and significant maintenance costs in Nuclear Power Plants (NPPs). In the framework of the Vibration ImpaKt In Nuclear power Generation (VIKING) consortium, Wall-Resolved LES (WR-LES) and Low-Reynolds Number UnsteadyRANS (LRN-URANS) combined to an Arbitrary Lagrangian Eulerian (ALE) approach have been used to predict FIV of a Single Flexible Tube in a Normal Square Tube Array. The pitch-to-diameter ratio is P/D=1.44. The cylinder motion uses a mass-spring-damper model, and a strong two-way coupling is performed. In all cases, the flow is fully turbulent, the computations are 3D and the transverse length is equal to 2D with periodic boundary conditions. WR-LES is performed on a restricted computational domain containing 3x7 tubes using a very fine mesh with a gap velocity of 1.5 m/s corresponding to a gap Reynolds number of 33 000. 3 corresponds to the number of tubes in the stream-wise direction for which a periodic boundary condition is applied. LRN-URANS are performed on the full 7x7 configuration at 1.5 m/s and 2.5 m/s. The LES is used as reference results for the low gap velocity. A strong dependency to the URANS model and the numerical options is highlighted. It is still not possible do discriminate the models but the advanced Eddy Viscosity Model (the BLv2k) and the second moment closure (EB-RSM) seem to exhibit a more satisfactory qualitative behavior. Finally, the presence of a bifurcation in the BLv2k computations is shown.
AB - In the context of nuclear engineering, Flow-Induced Vibration (FIV) in steam generators can lead to mechanical damage, responsible for safety issues and significant maintenance costs in Nuclear Power Plants (NPPs). In the framework of the Vibration ImpaKt In Nuclear power Generation (VIKING) consortium, Wall-Resolved LES (WR-LES) and Low-Reynolds Number UnsteadyRANS (LRN-URANS) combined to an Arbitrary Lagrangian Eulerian (ALE) approach have been used to predict FIV of a Single Flexible Tube in a Normal Square Tube Array. The pitch-to-diameter ratio is P/D=1.44. The cylinder motion uses a mass-spring-damper model, and a strong two-way coupling is performed. In all cases, the flow is fully turbulent, the computations are 3D and the transverse length is equal to 2D with periodic boundary conditions. WR-LES is performed on a restricted computational domain containing 3x7 tubes using a very fine mesh with a gap velocity of 1.5 m/s corresponding to a gap Reynolds number of 33 000. 3 corresponds to the number of tubes in the stream-wise direction for which a periodic boundary condition is applied. LRN-URANS are performed on the full 7x7 configuration at 1.5 m/s and 2.5 m/s. The LES is used as reference results for the low gap velocity. A strong dependency to the URANS model and the numerical options is highlighted. It is still not possible do discriminate the models but the advanced Eddy Viscosity Model (the BLv2k) and the second moment closure (EB-RSM) seem to exhibit a more satisfactory qualitative behavior. Finally, the presence of a bifurcation in the BLv2k computations is shown.
KW - Cross-flow
KW - FIV
KW - LRN-URANS
KW - Square Tube Array
KW - WR-LES
UR - https://www.scopus.com/pages/publications/85196621233
U2 - 10.13182/NURETH20-40433
DO - 10.13182/NURETH20-40433
M3 - Conference contribution
AN - SCOPUS:85196621233
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 4688
EP - 4701
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Y2 - 20 August 2023 through 25 August 2023
ER -