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Improving the modeling of near-wall interphase heat transfer in porous media models of Pebble Bed Reactors

Journal Article · · Nuclear Engineering and Design
 [1];  [2];  [3];  [4]
  1. Pennsylvania State Univ., University Park, PA (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  2. Pennsylvania State Univ., University Park, PA (United States)
  3. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  4. Texas A & M Univ., College Station, TX (United States)

Here, this work aims to improve capabilities for modeling localized effects in porous media models of Pebble Bed Reactors. The wall-channeling effect is the primary local phenomenon of interest in a PBR, where the presence of the reflector wall disrupts the pebble packing, causing the pebbles near the wall to pack less efficiently and creating large void regions. Accurate modeling of the near-wall region is important as it will affect core bypass flow and temperature predictions. Porous media models are commonly used for design scoping and plant-level simulations of PBRs. Although these models have some capabilities to model the near-wall region, the correlations that are available in porous media codes are often inaccurate when a multi-region model is used to discretize the near-wall region. This work employs a high-to-low analysis to study the accuracy of available interphase heat transfer closures. NekRS, a spectral element computational fluid dynamics code, is used to perform Large Eddy Simulations. These LES simulation results are compared to porous media model results from the Pronghorn porous media code. The friction term of the KTA drag closure is first improved, reducing the error in the prediction of the near-wall velocity from over 50% to less than 5%. This is combined with improvements to the form term from previous works to produce a drag closure that is capable of accurately modeling the wall-channeling effect across a variety of flow conditions. The Nusselt number predictions of several heat transfer correlations are compared to the high-fidelity results where it is found that the KTA heat transfer correlation is capable of accurately predicting the local Nusselt numbers that were determined in the high-fidelity simulation. Comparison of the radial solid temperature profiles, however, reveal discrepancies between NekRS and Pronghorn. It is discovered that the implementation of the interphase heat transfer coefficient that exists in many current porous media codes is not valid when local porosities are modeled. Instead, it is suggested that the interphase heat transfer coefficient should be dependent on the local porosity, the Nusselt number, and the local solid surface-to-volume ratio. Implementation of this change produces improvement in the agreement between the results obtained by NekRS and Pronghorn while using the KTA heat transfer correlation.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)
Grant/Contract Number:
AC07-05ID14517; AC05-00OR22725
OSTI ID:
2583243
Alternate ID(s):
OSTI ID: 2396789
Report Number(s):
INL/JOU--25-83274-Rev000
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: - Vol. 427; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (15)

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On numerical uncertainties in scale-resolving simulations of canonical wall turbulence journal September 2021
A robust and accurate outflow boundary condition for incompressible flow simulations on severely-truncated unbounded domains journal March 2014
Validation of Pronghorn friction-dominated porous media thermal-hydraulics model with the SANA experiments journal August 2019
Verification and validation of large eddy simulation with Nek5000 for cold leg mixing benchmark journal March 2020
An improved pressure drop correlation for modeling localized effects in a pebble bed reactor journal March 2023
MOOSE: Enabling massively parallel multiphysics simulation journal January 2020
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
Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics journal February 2021
Direct Numerical Simulation of the Flow Through a Randomly Packed Pebble Bed journal January 2020
Energy Exascale Computational Fluid Dynamics Simulations With the Spectral Element Method journal February 2024

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