Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Large Eddy Simulation of Convective Heat Transfer in a Random Pebble Bed Using the Spectral Element Method

Journal Article · · ASME Journal of Heat and Mass Transfer
DOI:https://doi.org/10.1115/1.4062940· OSTI ID:2447447
 [1];  [1];  [2];  [1];  [2];  [3];  [3]
  1. Pennsylvania State Univ., University Park, PA (United States)
  2. Argonne National Laboratory (ANL), Argonne, IL (United States)
  3. Kairos Power, Alameda, CA (United States)
The development of fluoride-cooled high-temperature reactors has drastically increased the demand for an in-depth understanding of the heat transfer (HT) in packed beds cooled by liquid salts. The complex flow fields and space-dependent porosity found in a pebble bed require a detailed understanding to ensure the proper cooling of the reactor core during normal and accident conditions. As detailed experimental data are complicated to obtain for these configurations, high-fidelity simulation such as large eddy simulation and direct numerical simulation (DNS) can be employed to create a high-resolution heat transfer numerical database that can assist in addressing industrial-driven issues associated with the heat transfer behavior of fluoride-cooled high-temperature reactors. In this paper, we performed a series of large eddy simulation using computational fluid dynamics (CFD) code NekRS to investigate the heat transfer for a bed of 1741 pebbles. Further, the characteristics of the flow, such as average, rms, and time series of velocity and temperature, have been analyzed. Porous media averages have also been performed. The simulation results show a good agreement between non-conjugate heat transfer and conjugate heat transfer. The generated data will be used to benchmark heat transfer modeling methods and local maxima/minima of heat transfer parameters. It will also be used for supporting convective heat transfer quantification for Kairos Power and benchmarking lower fidelity models.
Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
2447447
Journal Information:
ASME Journal of Heat and Mass Transfer, Journal Name: ASME Journal of Heat and Mass Transfer Journal Issue: 12 Vol. 145; ISSN 2832-8450
Publisher:
ASMECopyright Statement
Country of Publication:
United States
Language:
English

References (27)

Forced convection heat transfer correlations for flow in pipes, past flat plates, single cylinders, single spheres, and for flow in packed beds and tube bundles journal March 1972
Voidage variation in packed beds at small column to particle diameter ratio journal August 2003
Fixed bed catalytic reactor modelling-the radial heat transfer problem journal December 2011
Correlations for wall and particle shape effects on fixed bed bulk voidage journal October 1988
Druckverlust in Mehrkornschüttungen aus Kugeln journal February 1964
Effect of fluid dispersion coefficients on particle-to-fluid mass transfer coefficients in packed beds journal January 1978
Effect of fluid dispersion coefficients on particle-to-fluid heat transfer coefficients in packed beds journal January 1979
Non-darcian flow, heat and mass transfer in catalytic packed-bed reactors journal January 1990
A spectral element method for fluid dynamics: Laminar flow in a channel expansion journal June 1984
Technical design features and essential safety-related properties of the HTR-module journal July 1990
Heat and flow characteristics of packed beds journal January 1995
Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system journal January 2015
Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor journal May 2021
Generation IV nuclear reactors: Current status and future prospects journal October 2013
Wavelet analysis on the turbulent flow structure of a T-junction journal October 2018
Large eddy simulation in pebble bed gas cooled core reactors journal March 2008
Use of SANA experimental data for validation and verification of MGT-3D and a CFD porous media model for VHTR application journal August 2016
Validation of Pronghorn friction-dominated porous media thermal-hydraulics model with the SANA experiments journal August 2019
Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR) journal December 2021
NekRS, a GPU-accelerated spectral element Navier–Stokes solver journal December 2022
A Coupled DEM and CFD Simulation of Flow Field and Pressure Drop in Fixed Bed Reactor with Randomly Packed Catalyst Particles journal March 2009
Numerical Simulation of Low Mach Number Reactive Flows journal January 1997
Experimental investigation of cross flow mixing in a randomly packed bed and streamwise vortex characteristics using particle image velocimetry and proper orthogonal decomposition analysis journal February 2019
Toward Exascale: Overview of Large Eddy Simulations and Direct Numerical Simulations of Nuclear Reactor Flows with the Spectral Element Method in Nek5000 journal June 2020
Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors journal September 2022
Direct Numerical Simulation of the Flow Through a Randomly Packed Pebble Bed journal January 2020
Climate Signal Detection Using Wavelet Transform: How to Make a Time Series Sing journal December 1995

Similar Records

Large Eddy Simulation of Random Pebble Bed Using the Spectral Element Method
Technical Report · Wed Jun 01 00:00:00 EDT 2022 · OSTI ID:1878210

High Fidelity CFD Simulations Supporting the KP-FHR
Technical Report · Tue May 31 00:00:00 EDT 2022 · OSTI ID:2280640

High-Fidelity CFD Simulation of Mixed Convection and Forced Convection in a Pebble Bed Test Reactor Core
Journal Article · Mon Jan 27 19:00:00 EST 2025 · Nuclear Technology · OSTI ID:2997217