Coupled neutronics and thermal-hydraulics using TRUST-NK for high performance computing in molten salt reactor simulation

Molten Salt Reactors display a strong coupling between neutronics and thermal-hydraulics for which various simulation tools have been developed. In this paper we describe TRUST-NK, a neutronics code based on TRUST, CEA’s High Performance Computing (HPC) platform. TRUST-NK provides a multi-group diffusion solver with transport of delayed neutron precursors, for both steady-state and transient simulations. Being based on TRUST allows TRUST-NK to take advantage of the platform’s HPC capabilities and to easily couple to CFD solvers provided by other derivatives of TRUST. After a brief description of the code, we present an example of application to a simplified MSR model.

Publication Details

Journal
Springer Link (Chiba Institute of Technology)
Published
2024-10-15
DOI
https://doi.org/10.1051/epjconf/202430203007/pdf
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Coupled neutronics and thermal-hydraulics using TRUST-NK for high performance computing in molten salt reactor simulation

Springer Link (Chiba Institute of Technology)
Nuclear reactor physics and engineering
article

Coupled neutronics and thermal-hydraulics using TRUST-NK for high performance computing in molten salt reactor simulation

article en

Abstract

Molten Salt Reactors display a strong coupling between neutronics and thermal-hydraulics for which various simulation tools have been developed. In this paper we describe TRUST-NK, a neutronics code based on TRUST, CEA’s High Performance Computing (HPC) platform. TRUST-NK provides a multi-group diffusion solver with transport of delayed neutron precursors, for both steady-state and transient simulations. Being based on TRUST allows TRUST-NK to take advantage of the platform’s HPC capabilities and to easily couple to CFD solvers provided by other derivatives of TRUST. After a brief description of the code, we present an example of application to a simplified MSR model.

Springer Link (Chiba Institute of Technology)
Openalex Percentile: Top 37%
Nuclear reactor physics and engineering
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