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Preliminary Analysis on Thermal-Hydraulic Behavior of PBR Cores Using DEM-CFD Coupled Method

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Obtaining particle wise information of each PBR fuel would enhance accuracy in predictions for pebble locations, and pebble temperatures. However, the discrete modeling of thermal pebble behavior is complicated, and would take excessive computational time. Moreover, the packed state of PBR core, a pebble bed assembly may affect and be affected by the neutronic, thermal behavior of individual pebbles, leading to the need for a three-way coupling of mechanics, thermal hydraulics, and neutronics. In this study, a new DEM model has been developed to model interactions in packed bed systems in a mechanical, thermal point of view. A simplified radiative model was proposed, where the effective radiation range exhibited high accuracy for independent experiments at a value of 3.5rrpp. Moreover, a 4-mesh Finite Differential Scheme was applied to model internal conduction, and thermal expansion of fuels, which showed an error rate less than 7% compared to the analytical solution, while saving computational time. The DEM model was then coupled with a CFD code to simulate interactions in a solid-fluid two phase media. Where the results were compared with benchmark data of pressure drop and cooling in a packed pebble bed. Finally, a preliminary analysis was made for a PBR core by coupling a DEM/DEM-CFD with a neutronics code to obtain the temperature and packed state of the core based on the power distribution data. The feasibility of the DEM-Neutronic model was found sufficient, where further studies could be extended to the modeling of a more realistic PBR core.

Original languageEnglish
Title of host publicationProceedings of the 2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024
PublisherAmerican Nuclear Society
Pages880-889
Number of pages10
ISBN (Electronic)9780894487996
DOIs
Publication statusPublished - 2024
Event2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024 - Las Vegas, United States
Duration: 16 Jun 202419 Jun 2024

Publication series

NameProceedings of the 2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024

Conference

Conference2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024
Country/TerritoryUnited States
CityLas Vegas
Period16/06/2419/06/24

Bibliographical note

Publisher Copyright:
© ICAPP 2024.All rights reserved.

Keywords

  • Coupling
  • Discrete Element Method
  • GPU
  • PBR
  • Smoothed Particle Hydrodynamics

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