Review of researches on coupled system and CFD codes

Long, Jianping; Zhang, Bin; Yang, Baohui; Wang, Sipeng

doi:10.1016/j.net.2021.03.027

Cited by 19 publications

(3 citation statements)

References 27 publications

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“…It was demonstrated that Star-CCM+ can predict well the effects of thermal loads in geometries. Again, [ 109 ] reviewed CFD and coupled system codes such as RELAP-3D that include 3D modules with limited capacity for 3D simulation. The review discussed the way validation and verification work for coupled codes as determined by the exchange of information between CFD and system codes.…”

Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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“…A number of studies are available in the literature on coupled system/CFD codes for thermal-hydraulics and safety analyses for nuclear reactors. Methods of coupling, of data transfer processing between CFD and system codes, as well as validation procedures have been reviewed in [159] and they may also be applied in fusion engineering.…”

Section: Conclusion and Future Randdmentioning

confidence: 99%

MHD R&D Activities for Liquid Metal Blankets

et al. 2021

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According to the most recently revised European design strategy for DEMO breeding blankets, mature concepts have been identified that require a reduced technological extrapolation towards DEMO and will be tested in ITER. In order to optimize and finalize the design of test blanket modules, a number of issues have to be better understood that are related to the magnetohydrodynamic (MHD) interactions of the liquid breeder with the strong magnetic field that confines the fusion plasma. The aim of the present paper is to describe the state of the art of the study of MHD effects coupled with other physical phenomena, such as tritium transport, corrosion and heat transfer. Both numerical and experimental approaches are discussed, as well as future requirements to achieve a reliable prediction of these processes in liquid metal blankets.

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“…All of these are system level codes which are all generally 1-D (some simplified two-or three-dimensional versions also exist). However, to effectively simulate the details of the fluid flow, proper computational fluid dynamics (CFD) studies need to be performed using three-dimensional simulation with high accuracy [15].…”

Section: Introductionmentioning

confidence: 99%

A Thermal Approach for Modelling the Concrete Ablation during Molten Corium-Concrete Interaction

Khurshid,

Hassan,

Faizan

et al. 2024

Preprint

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An accident in a nuclear power plant involving a reactor core meltdown would result in instigation of molten corium, which is a mixture of nuclear fuel, claddings and structural components. In this paper, an enthalpy porosity model is proposed to comprehensively analyze the ablation of concrete during the Molten Corium and Concrete Interaction (MCCI) process. The developed numerical model is an extension of the enthalpy-porosity model and is termed as Corium-Concrete Enthalpy Porosity Model (CCEPM). The developed CCEPM Computational Fluid Dynamic (CFD) model can predict natural convection, melting and solidification. The developed model simplifies the complex phenomena of concrete ablation and its melting by incorporating the multi-region approach. The model was implemented in OpenFOAM, by developing a new solver which couples the buoyant-driven natural convection and conjugate heat transfer solvers. The thermal modelling and heat transfer capabilities of the developed solver were verified against experimental data sets. Additionally, the effect of various boundary conditions, concrete thermal conductivity and intensity of decay heat were analyzed to study their impact on concrete ablation. We observed significant low concrete ablation, controlled temperature and velocity field, for the water-cooled boundary condition. Accordingly, the ablation of concrete decreased by 17% just by imposing the water-cooled boundary condition. Similarly, when the thermal conductivity was decreased to 0.43 and 0.13 W/m. K, the ablation of concrete reduced by 38% and 75%, respectively. Furthermore, early cooling of molten corium to decrease decay heat was found to be an effective strategy to mitigate the concrete ablation successfully by 20%.

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Review of researches on coupled system and CFD codes

Cited by 19 publications

References 27 publications

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Liquid metal cooled fast reactor thermal hydraulic research development: A review

MHD R&D Activities for Liquid Metal Blankets

A Thermal Approach for Modelling the Concrete Ablation during Molten Corium-Concrete Interaction

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