Hydraulic benchmark data for PWR mixing vane grid

Conner, Michael E.; Hassan, Yassin A.; Dominguez-Ontiveros, Elvis E.

doi:10.1016/j.nucengdes.2012.12.001

Cited by 57 publications

(21 citation statements)

References 5 publications

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“…There is a vortex pair that is responsible for the strong swirling flow with an elliptical shape. This lateral velocity distribution was also observed qualitatively in the PIV measurements of Conner et al (2013), see Fig. 12b.…”

Section: Resultssupporting

confidence: 78%

Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers

Zimmermann

Otić

et al. 2015

Annals of Nuclear Energy

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Section: Resultssupporting

confidence: 78%

Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers

Zimmermann

Otić

et al. 2015

Annals of Nuclear Energy

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“…Not shown here are the exterior walls of the flow housing used in the experimental facility. Additional details on the experimental configuration and results may be found in Conner, et al [23] and Yan, et al [21].…”

Section: Les On the 5 × 5 Spider Meshesmentioning

confidence: 99%

Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors

Bakosi

Christon

Lowrie

et al. 2013

Nuclear Engineering and Design

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The grid-to-rod fretting (GTRF) problem in pressurized water reactors is a flow-induced vibration problem that results in wear and failure of the fuel rods in nuclear assemblies. In order to understand the fluid dynamics of GTRF and to build an archival database of turbulence statistics for various configurations, implicit large-eddy simulations of time-dependent single-phase turbulent flow have been performed in 3 × 3 and 5 × 5 rod bundles with a single grid spacer. To assess the computational mesh and resolution requirements, a method for quantitative assessment of unstructured meshes with no-slip walls is described. The calculations have been carried out using Hydra-TH, a thermal-hydraulics code developed at Los Alamos for the Consortium for Advanced Simulation of Light water reactors, a United States Department of Energy Innovation Hub. Hydra-TH uses a second-order implicit incremental projection method to solve the singlephase incompressible Navier-Stokes equations. The simulations explicitly resolve the large scale motions of the turbulent flow field using first principles and rely on a monotonicity-preserving numerical technique to represent the unresolved scales. Each series of simulations for the 3 × 3 and 5 × 5 rod-bundle geometries is an analysis of the flow field statistics combined with a mesh-refinement study and validation with available experimental data. Our primary focus is the time history and statistics of the forces loading the fuel rods. These hydrodynamic forces are believed to be the key player resulting in rod vibration and GTRF wear, one of the leading causes for leaking nuclear fuel which costs power utilities millions of dollars in preventive measures. We demonstrate that implicit large-eddy simulation of rod-bundle flows is a viable way to calculate the excitation forces for the GTRF problem.

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“…The experimental results indicated that unknown flow distributions developed by the spacer grids could be captured by the experiments and these results could be used as fundamental information of the CFD calculation. On the other hand, the CFD calculation methodologies based on the experimental studies have been widely conducted [6,7]. The lateral field velocity along the flow direction in a single subchannel showed good agreement between the PIV and the CFD results, by comparing the center of vortices, same vortex rotation, same rod swirling flow, and same inter-assembly flow direction in gap.…”

Section: Introductionmentioning

confidence: 96%

“…The studies [1][2][3][4][5][6][7][8][9] were based on the actual shape of the spacer grids used in nuclear power plants. On the other hand, there are studies related to new types of spacer grids to enhance CHF and heat transfer performance by increasing secondary flows and centrifugal force in the subchannels.…”

Section: Introductionmentioning

confidence: 99%

Swirling performance of flow-driven rotating mixing vane toward critical heat flux enhancement

Seo

Park

Seo

et al. 2015

International Journal of Heat and Mass Transfer

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Hydraulic benchmark data for PWR mixing vane grid

Cited by 57 publications

References 5 publications

Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers

Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers

Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors

Swirling performance of flow-driven rotating mixing vane toward critical heat flux enhancement

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