Multiphysics Modelling of the Molten Salt Fast Reactor using NekRS and the Fission Matrix Method

Fuente: arXiv
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Main Authors: Dalinger, Maximiliano, Merzari, Elia, Lee, Saya
Format: Preprint
Published: 2026
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author Dalinger, Maximiliano
Merzari, Elia
Lee, Saya
author_facet Dalinger, Maximiliano
Merzari, Elia
Lee, Saya
contents The Molten Salt Fast Reactor (MSFR) has the particularity that the coolant is also the fuel, which tightens the coupling between neutronics and thermal hydraulics as the fuel circulates through the primary system. Therefore, developing computational models to analyze the MSFR requires a multiphysics approach. In this paper, we propose developing a neutronic thermal-hydraulic computational model of the MSFR that uses a reduced-order model to solve the neutronics equations. The principal computational tool chosen for this purpose is the high-fidelity code Cardinal, a wrapping within the MOOSE framework that integrates the Computational Fluid Dynamics code NekRS and the Monte Carlo particle transport code OpenMC. However, we use the Fission Matrix (FM) Method to solve the neutronics equations instead of OpenMC. The FM method can perform fast and still accurate neutronics simulations. It relies on precalculated databases obtained through a Monte Carlo simulation.
format Preprint
id arxiv_https___arxiv_org_abs_2602_18626
institution arXiv
publishDate 2026
record_format arxiv
spellingShingle Multiphysics Modelling of the Molten Salt Fast Reactor using NekRS and the Fission Matrix Method
Dalinger, Maximiliano
Merzari, Elia
Lee, Saya
Computational Physics
The Molten Salt Fast Reactor (MSFR) has the particularity that the coolant is also the fuel, which tightens the coupling between neutronics and thermal hydraulics as the fuel circulates through the primary system. Therefore, developing computational models to analyze the MSFR requires a multiphysics approach. In this paper, we propose developing a neutronic thermal-hydraulic computational model of the MSFR that uses a reduced-order model to solve the neutronics equations. The principal computational tool chosen for this purpose is the high-fidelity code Cardinal, a wrapping within the MOOSE framework that integrates the Computational Fluid Dynamics code NekRS and the Monte Carlo particle transport code OpenMC. However, we use the Fission Matrix (FM) Method to solve the neutronics equations instead of OpenMC. The FM method can perform fast and still accurate neutronics simulations. It relies on precalculated databases obtained through a Monte Carlo simulation.
title Multiphysics Modelling of the Molten Salt Fast Reactor using NekRS and the Fission Matrix Method
topic Computational Physics
url https://arxiv.org/abs/2602.18626