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High-Fidelity Neutronics/Thermal Hydraulics/Pebble Flow Coupling Simulation of Pebble Bed Reactor HTR-PM.

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Title: High-Fidelity Neutronics/Thermal Hydraulics/Pebble Flow Coupling Simulation of Pebble Bed Reactor HTR-PM.
Authors: Li, Ruihan1 (AUTHOR) jingang@tsinghua.edu.cn, Chen, Junyi1 (AUTHOR), Zhu, Aixin1,2 (AUTHOR), Liang, Jingang1 (AUTHOR), She, Ding1 (AUTHOR), Zhang, Hongjian1 (AUTHOR)
Source: Nuclear Science & Engineering. Nov2025, Vol. 199 Issue 11, p1954-1970. 17p.
Subjects: Pebble bed reactors, Thermal hydraulics, Monte Carlo method, Discrete element method, Granular flow, Gas cooled reactors, Neutrons, Computational fluid dynamics
Abstract: Simulating pebble bed reactors with high fidelity presents significant challenges because of the intricate geometry of the randomly packed pebbles and the requirement for multiphysics coupling. This study introduces an innovative modeling framework that couples neutronics, thermal hydraulics, and pebble flow dynamics of the reactor core. The Monte Carlo (MC) code, computational fluid dynamics (CFD) method, and discrete element method (DEM) are used, utilizing the open-source codes OpenMC, OpenFOAM, and LAMMPS, respectively. The core geometry is explicitly constructed for both the MC and the DEM models, while a porous media approach is adopted for the CFD model to manage computational expenses. Enhancements have been made to OpenMC to facilitate data exchange: The core geometry is allowed to change between depletion steps to simulate pebble motion, and a temperature mesh scheme has been developed for efficient temperature distribution transfer. Validations are provided for the models and modifications implemented in this study. As a practical demonstration, a depletion simulation on a full-core model of a High-Temperature Gas-Cooled Reactor–Pebble-Bed Module (HTR-PM) is conducted, explicitly modeling 420 000 randomly packed fuel pebbles. The results reveal detailed distributions of power, temperature, and burnup, all consistent with expected physical behavior, underscoring the effectiveness of our approach. [ABSTRACT FROM AUTHOR]
Copyright of Nuclear Science & Engineering is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
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Header DbId: egs
DbLabel: Engineering Source
An: 188362692
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
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  Data: High-Fidelity Neutronics/Thermal Hydraulics/Pebble Flow Coupling Simulation of Pebble Bed Reactor HTR-PM.
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  Data: <searchLink fieldCode="AR" term="%22Li%2C+Ruihan%22">Li, Ruihan</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> jingang@tsinghua.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Chen%2C+Junyi%22">Chen, Junyi</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zhu%2C+Aixin%22">Zhu, Aixin</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Liang%2C+Jingang%22">Liang, Jingang</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22She%2C+Ding%22">She, Ding</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Zhang%2C+Hongjian%22">Zhang, Hongjian</searchLink><relatesTo>1</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Science+%26+Engineering%22">Nuclear Science & Engineering</searchLink>. Nov2025, Vol. 199 Issue 11, p1954-1970. 17p.
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  Data: <searchLink fieldCode="DE" term="%22Pebble+bed+reactors%22">Pebble bed reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Thermal+hydraulics%22">Thermal hydraulics</searchLink><br /><searchLink fieldCode="DE" term="%22Monte+Carlo+method%22">Monte Carlo method</searchLink><br /><searchLink fieldCode="DE" term="%22Discrete+element+method%22">Discrete element method</searchLink><br /><searchLink fieldCode="DE" term="%22Granular+flow%22">Granular flow</searchLink><br /><searchLink fieldCode="DE" term="%22Gas+cooled+reactors%22">Gas cooled reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Neutrons%22">Neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Computational+fluid+dynamics%22">Computational fluid dynamics</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Simulating pebble bed reactors with high fidelity presents significant challenges because of the intricate geometry of the randomly packed pebbles and the requirement for multiphysics coupling. This study introduces an innovative modeling framework that couples neutronics, thermal hydraulics, and pebble flow dynamics of the reactor core. The Monte Carlo (MC) code, computational fluid dynamics (CFD) method, and discrete element method (DEM) are used, utilizing the open-source codes OpenMC, OpenFOAM, and LAMMPS, respectively. The core geometry is explicitly constructed for both the MC and the DEM models, while a porous media approach is adopted for the CFD model to manage computational expenses. Enhancements have been made to OpenMC to facilitate data exchange: The core geometry is allowed to change between depletion steps to simulate pebble motion, and a temperature mesh scheme has been developed for efficient temperature distribution transfer. Validations are provided for the models and modifications implemented in this study. As a practical demonstration, a depletion simulation on a full-core model of a High-Temperature Gas-Cooled Reactor–Pebble-Bed Module (HTR-PM) is conducted, explicitly modeling 420 000 randomly packed fuel pebbles. The results reveal detailed distributions of power, temperature, and burnup, all consistent with expected physical behavior, underscoring the effectiveness of our approach. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Nuclear Science & Engineering is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1080/00295639.2025.2471712
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 17
        StartPage: 1954
    Subjects:
      – SubjectFull: Pebble bed reactors
        Type: general
      – SubjectFull: Thermal hydraulics
        Type: general
      – SubjectFull: Monte Carlo method
        Type: general
      – SubjectFull: Discrete element method
        Type: general
      – SubjectFull: Granular flow
        Type: general
      – SubjectFull: Gas cooled reactors
        Type: general
      – SubjectFull: Neutrons
        Type: general
      – SubjectFull: Computational fluid dynamics
        Type: general
    Titles:
      – TitleFull: High-Fidelity Neutronics/Thermal Hydraulics/Pebble Flow Coupling Simulation of Pebble Bed Reactor HTR-PM.
        Type: main
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          Name:
            NameFull: Li, Ruihan
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            NameFull: Chen, Junyi
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            NameFull: Zhu, Aixin
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            NameFull: Liang, Jingang
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            NameFull: She, Ding
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            NameFull: Zhang, Hongjian
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            – D: 01
              M: 11
              Text: Nov2025
              Type: published
              Y: 2025
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              Value: 199
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              Value: 11
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            – TitleFull: Nuclear Science & Engineering
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