Development of coupled PROTEUS-NODAL and SAM code system for multiphysics analysis of molten salt reactors

Yang, Gang; Jaradat, Mustafa K.; Yang, Won Sik; Lee, Chang-Ho

doi:10.1016/j.anucene.2021.108889

Cited by 12 publications

(3 citation statements)

References 33 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Moltres [7], an application for modeling MSRs based on the MOOSE framework [8], used the multigroup diffusion equation in 3D or axisymmetric 2D coupled with the heat equation and the one-dimensional (1D) DNPs drift model. Yang et al [9] developed a framework for coupling a 3D neutron transport code PROTEUS-NODAL [10] and a modern system-level thermal-hydraulics code SAM [11] to simulate steady-state and transients of MSRs.…”

Section: Introductionmentioning

confidence: 99%

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations

Elhareef,

Wu,

Fratoni

2023

JNE

View full text Add to dashboard Cite

Molten Salt Reactors (MSRs) have recently gained resurged research and development interest in the advanced reactor community. Several computational tools are being developed to capture the strong neutronics/thermal-hydraulics coupling effect in this special reactor configuration. This paper presents a consistent one-dimensional (1D) multigroup neutron diffusion model for MSR analysis, with the primary aim for fast and accurate calculations for long transients, as well as sensitivity and uncertainty analysis of the reactor. A fictitious radial leakage cross section is introduced in the model to properly account for the radial leakage effects of the reactor. The leakage cross section and other consistent neutronics parameters are generated with the Monte Carlo code Serpent using high-fidelity three-dimensional (3D) models. The accuracy of the 1D consistent model is verified by the reference solution from the Monte Carlo model on the Molten Salt Reactor Experiment (MSRE) configuration. The 1D consistent model successfully reproduced the integrated flux from the 3D model and the reactor multiplication factor keff with the error in the range of 95 to 397 pcm (per cent mille), depending on discretized energy group structures. The developed model is also extended to estimate the reactivity loss due to fuel circulation in MSRE. The estimate of reactivity loss in dynamics analysis is in great agreement with the experimental data. This model functions as the first step in the development of a 1D fully neutronics/thermal-hydraulics coupled model for short- and long-term MSRE transient analysis.

show abstract

Section: Introductionmentioning

confidence: 99%

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations

Elhareef,

Wu,

Fratoni

2023

JNE

View full text Add to dashboard Cite

show abstract

“…Similar studies have also been conducted using different tools, including COMSOL (Fiorina et al, 2014) and some in-house codes (see Tiberga et al, 2020). In the US, tools for MSRs have been developed for instance based on the MOOSE framework (Yang et al, 2022;Lindsay et al, 2018) and on the GOTHIC software package (Harvill et al, 2022).…”

Section: Introductionmentioning

confidence: 99%

On the Need for Multi-Dimensional Models for the Safety Analysis of (Fast-Spectrum) Molten Salt Reactors

Habtemariam,

Fiorina,

Lorenzi

et al. 2023

Preprint

View full text Add to dashboard Cite

“…Most of research on recent multiphysics tools mentioned previously has been conducted to revisit the MSRE, to perform design studies of LFMSRs mainly using fluoride-based salt, to simulate particular phenomenon such as solid particle or inert gas transport, 12,13 or to extend existing software or codes developed for a MSR updating coupling scheme between neutronics and thermal hydraulics. [14][15][16] Transient simulations of LFMSRs using those multiphysics tools have been focused on the core domain only to assess whether such a design meets the safety criteria from maximum temperature of the fuel salt. 8,17 Recent LFMSR designs targeting near-term deployment adopt chloride-based salt because of its advantages in the economic utilization of the fissile materials 18 and cost-effective fuel fabrication using techniques like pyroprocessing.…”

Section: Introductionmentioning

confidence: 99%

Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors

Jeong

Shirvan

Buric

2022

Nuclear Science and Engineering

View full text Add to dashboard Cite

This work establishes a generic multiphysics tool for liquid-fueled molten salt reactors (LFMSRs) to select key installation locations and specify the expected operating temperature range for the development of advanced instrumentation and control systems, particularly distributed temperature sensors using fiber optics. A commercial computation fluid dynamics package (STAR-CCM+) is used to formulate a neutronics and thermal-hydraulic coupled solver, showing good agreement with a recent benchmark problem developed for evaluating the coupling methodology of neutronics and thermal hydraulics. The multiphysics model is then applied to the reference molten chloride salt fast reactor (MCFR) design under development by TerraPower based on publicly available information. The available twodimensional axisymmetric model for the reactor core is used for coupling calculations, and system component details are leveraged using the lumped method to complete the energy balance. The dynamic responses of the MCFR model are investigated during operational transients, such as unprotected loss-offlow and uniform perturbation scenarios. Maximum temperature and local temperature distributions are characterized during unprotected loss of flow and unprotected loss of heat sink events. The thermal responses of the fuel salt and core components are analyzed from induced perturbation of the system parameters, such as the flow rate and the heat sink capacity. The results motivate the use of continuous monitoring of the temperature variation in real time along the reflector region with the use of fiber optics to validate the multiphysics code to support a reactor's licensing basis, as well as to support the structural longevity and improve safety in LFMSRs.

show abstract

Development of coupled PROTEUS-NODAL and SAM code system for multiphysics analysis of molten salt reactors

Cited by 12 publications

References 33 publications

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations

On the Need for Multi-Dimensional Models for the Safety Analysis of (Fast-Spectrum) Molten Salt Reactors

Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors

Contact Info

Product

Resources

About