TY - GEN
T1 - LES AND RANS MODELING OF AN 84-PIN HEXAGONAL ROD BUNDLE WITH SPACER GRID
AU - Kraus, Adam R.
AU - Merzari, Elia
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - As part of an ongoing Integrated Research Project (IRP), detailed investigations of the flow and heat transfer characteristics of an 84-pin hexagonal rod bundle representing a potential modular gas-cooled fast reactor design have been performed. The rod bundle features P/D of 1.5 and a large central guide tube, along with simple spacer grids and an outer enclosure. The primary focus of the current work is modeling and simulation of this geometry using a range of computational techniques. These include high-fidelity Large Eddy Simulation (LES) and Reynolds-Averaged Navier-Stokes (RANS) approaches. The flow predictions are validated at Reynolds number of roughly 12000 using matched index of refraction Particle Image Velocimetry (PIV) experimental data that were also generated as part of the IRP. Many characteristics of the experimental flow are replicated in the LES and RANS runs, and a general agreement between simulation and experiment is shown. The LES shows notably better agreement with the turbulent kinetic energy downstream of the grid as compared to RANS. The experimental and high-fidelity data will be used to inform the closures for a novel multiscale methodology. The high-level goal of the work is to use the high-fidelity data to yield improved multiscale thermal analysis techniques for solving fuel performance problems of direct relevance to industry.
AB - As part of an ongoing Integrated Research Project (IRP), detailed investigations of the flow and heat transfer characteristics of an 84-pin hexagonal rod bundle representing a potential modular gas-cooled fast reactor design have been performed. The rod bundle features P/D of 1.5 and a large central guide tube, along with simple spacer grids and an outer enclosure. The primary focus of the current work is modeling and simulation of this geometry using a range of computational techniques. These include high-fidelity Large Eddy Simulation (LES) and Reynolds-Averaged Navier-Stokes (RANS) approaches. The flow predictions are validated at Reynolds number of roughly 12000 using matched index of refraction Particle Image Velocimetry (PIV) experimental data that were also generated as part of the IRP. Many characteristics of the experimental flow are replicated in the LES and RANS runs, and a general agreement between simulation and experiment is shown. The LES shows notably better agreement with the turbulent kinetic energy downstream of the grid as compared to RANS. The experimental and high-fidelity data will be used to inform the closures for a novel multiscale methodology. The high-level goal of the work is to use the high-fidelity data to yield improved multiscale thermal analysis techniques for solving fuel performance problems of direct relevance to industry.
UR - http://www.scopus.com/inward/record.url?scp=85188310886&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85188310886&partnerID=8YFLogxK
U2 - 10.13182/NURETH20-40164
DO - 10.13182/NURETH20-40164
M3 - Conference contribution
AN - SCOPUS:85188310886
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 352
EP - 365
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 -