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

Abstract

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 andmore » 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. As a result, we demonstrate that implicit large-eddy simulation of rod-bundle flows is a viable way to calculate the excitation forces for the GTRF problem.« less

Authors:
 [1];  [1];  [1];  [1];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1233158
Report Number(s):
LA-UR-12-26572
Journal ID: ISSN 0029-5493; PII: S0029549313003129
Grant/Contract Number:  
AC52-06NA25396
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 262; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Bakosi, J., Christon, M. A., Lowrie, R. B., Pritchett-Sheats, L. A., and Nourgaliev, R. R.. Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors. United States: N. p., 2013. Web. https://doi.org/10.1016/j.nucengdes.2013.06.007.
Bakosi, J., Christon, M. A., Lowrie, R. B., Pritchett-Sheats, L. A., & Nourgaliev, R. R.. Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors. United States. https://doi.org/10.1016/j.nucengdes.2013.06.007
Bakosi, J., Christon, M. A., Lowrie, R. B., Pritchett-Sheats, L. A., and Nourgaliev, R. R.. Fri . "Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors". United States. https://doi.org/10.1016/j.nucengdes.2013.06.007. https://www.osti.gov/servlets/purl/1233158.
@article{osti_1233158,
title = {Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors},
author = {Bakosi, J. and Christon, M. A. and Lowrie, R. B. and Pritchett-Sheats, L. A. and Nourgaliev, R. R.},
abstractNote = {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. As a result, we demonstrate that implicit large-eddy simulation of rod-bundle flows is a viable way to calculate the excitation forces for the GTRF problem.},
doi = {10.1016/j.nucengdes.2013.06.007},
journal = {Nuclear Engineering and Design},
number = C,
volume = 262,
place = {United States},
year = {2013},
month = {7}
}

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Works referenced in this record:

Numerical simulation of turbulent flow through a 37-element CANDU fuel bundle
journal, February 2012


CFD methodology and validation for single-phase flow in PWR fuel assemblies
journal, September 2010


Fluctuating pressure calculation induced by axial flow trough mixing grid
journal, January 2012


Decay of Swirling Turbulent Flow in Rod-bundle
journal, January 2006

  • Ikeno, Tsutomu; Kajishima, Takeo
  • Journal of Fluid Science and Technology, Vol. 1, Issue 1
  • DOI: 10.1299/jfst.1.36

A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16×16KOFA fuel
journal, April 2010


Numerical simulation of the fluid–structure interaction for two simple fuel assemblies
journal, May 2013


Modelling of fuel bundle vibration and the associated fretting wear in a CANDU fuel channel
journal, November 2013


A review of flow-induced vibrations in reactors and reactor components
journal, January 1983


A new method to predict Grid-To-Rod Fretting in a PWR fuel assembly inlet region
journal, August 2011


Large eddy simulation of turbulent flow surrounding two simulated CANDU fuel bundles
journal, September 2011


    Works referencing / citing this record:

    Direct Numerical Simulation and Wall-Resolved Large Eddy Simulation in Nuclear Thermal Hydraulics
    journal, June 2019