Thermomechanics coupling to Monte Carlo particle transport on unstructured mesh geometries using Cardinal

Geometry deformation due to thermal expansion influences neutron transport in many systems. Studying this phenomenon involves coupling models for neutronics, thermal hydraulics, and solid mechanics. To enable high fidelity modeling of these coupled physics, new capabilities were introduced in Cardinal, coupling OpenMC Monte Carlo particle transport models with MOOSE thermomechanical physics on unstructured moving-mesh geometries. In this work, we present a fully open-source capability leveraging on-the-fly mesh skinning to automatically regenerate OpenMC geometry, which allows multiphysics feedback from temperature, density, and geometry changes. The new capability is verified using an analytic benchmark slab problem, which couples S 2 neutron transport with thermal conduction, convective boundary conditions, Doppler-broadened cross sections, and nonlinear thermal expansion effects along the heated slab. Cardinal reproduces the analytic solutions for the neutron flux, heating, k eff , and temperature with demonstrated convergence in various error terms including mesh resolution and cross section temperature library spacing. For the nominal benchmark conditions and with a fine mesh, maximum relative errors for neutron flux, temperature, and heating are lower than 1%, while errors in integral quantities such as k eff and slab length are within 1 pcm and 48 µm, respectively. This work (i) presents a new numerical approach to thermomechanics coupling with OpenMC models, (ii) is the first (to our knowledge) to utilize a mechanical partial differential equation (PDE) solution to solve the (Griesheimer and Kooreman, 2022) analytic benchmark, and (iii) develops this verified capability within an open-source package. • Open-source capability to support thermomechanics coupling to Monte Carlo particle transport. • On-the-fly mesh skinning to automatically regenerate OpenMC geometry following mesh movement. • Verified using the Griesheimer and Kooreman multiphysics analytic benchmark.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-12-31
DOI
https://doi.org/10.1016/j.anucene.2025.112068
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Thermomechanics coupling to Monte Carlo particle transport on unstructured mesh geometries using Cardinal

April Novak, Pierre-Clément A. Simon, Mahmoud Eltawila, Helen Brooks et al.
Annals of Nuclear Energy
Nuclear reactor physics and engineering
article

Thermomechanics coupling to Monte Carlo particle transport on unstructured mesh geometries using Cardinal

April Novak, Pierre-Clément A. Simon, Mahmoud Eltawila, Helen Brooks, Guillaume L. Giudicelli, Nicholas Wozniak
article en

Abstract

Geometry deformation due to thermal expansion influences neutron transport in many systems. Studying this phenomenon involves coupling models for neutronics, thermal hydraulics, and solid mechanics. To enable high fidelity modeling of these coupled physics, new capabilities were introduced in Cardinal, coupling OpenMC Monte Carlo particle transport models with MOOSE thermomechanical physics on unstructured moving-mesh geometries. In this work, we present a fully open-source capability leveraging on-the-fly mesh skinning to automatically regenerate OpenMC geometry, which allows multiphysics feedback from temperature, density, and geometry changes. The new capability is verified using an analytic benchmark slab problem, which couples S 2 neutron transport with thermal conduction, convective boundary conditions, Doppler-broadened cross sections, and nonlinear thermal expansion effects along the heated slab. Cardinal reproduces the analytic solutions for the neutron flux, heating, k eff , and temperature with demonstrated convergence in various error terms including mesh resolution and cross section temperature library spacing. For the nominal benchmark conditions and with a fine mesh, maximum relative errors for neutron flux, temperature, and heating are lower than 1%, while errors in integral quantities such as k eff and slab length are within 1 pcm and 48 µm, respectively. This work (i) presents a new numerical approach to thermomechanics coupling with OpenMC models, (ii) is the first (to our knowledge) to utilize a mechanical partial differential equation (PDE) solution to solve the (Griesheimer and Kooreman, 2022) analytic benchmark, and (iii) develops this verified capability within an open-source package. • Open-source capability to support thermomechanics coupling to Monte Carlo particle transport. • On-the-fly mesh skinning to automatically regenerate OpenMC geometry following mesh movement. • Verified using the Griesheimer and Kooreman multiphysics analytic benchmark.

Annals of Nuclear EnergyVol. 229
Argonne National Laboratory (US), University of Illinois Urbana-Champaign (US), Idaho National Laboratory (US), United Kingdom Atomic Energy Authority (GB)
Openalex Percentile: Top 19%
Nuclear reactor physics and engineering
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