Academic literature on the topic 'Modèle CFD Code_Saturne'

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Journal articles on the topic "Modèle CFD Code_Saturne"

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Qu, Yongfeng, Maya Milliez, Luc Musson-Genon, and Bertrand Carissimo. "Modelling Radiative and Convective Thermal Exchanges over a European City Center and Their Effects on Atmospheric Dispersion." Sustainability 14, no. 12 (2022): 7295. http://dx.doi.org/10.3390/su14127295.

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Micro-meteorological studies of urban flow and pollution dispersion often assume a neutral atmosphere and often the three-dimensional variation in temperature fields and flow around buildings is neglected in most building energy balance models. The aim of this work is to present the results of development and validation of a three-dimensional tool coupling thermal energy balance of the buildings and modelling of the atmospheric flow and dispersion in urban areas. To do so, a 3D microscale atmospheric radiative scheme has been developed in the atmospheric module of the computational fluid dynam
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Dissertations / Theses on the topic "Modèle CFD Code_Saturne"

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Alam, Boulos. "Modélisation numérique de la turbulence et de la dispersion atmosphérique par faibles vents en milieu urbain." Electronic Thesis or Diss., université Paris-Saclay, 2023. https://www.biblio.univ-evry.fr/theses/2023/interne/2023UPAST179.pdf.

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Cette thèse se situe dans le contexte de la modélisation de la dispersion atmosphérique, en particulier en présence de vents faibles. Les sources de pollution atmosphérique, souvent situées près du sol et influencées par des obstacles complexes, engendrent des concentrations élevées de polluants à proximité, ce qui se traduit par des fluctuations significatives de ces concentrations. Les vents faibles, généralement associés à des conditions atmosphériques stables, posent un défi particulier en matière de modélisation de la dispersion des polluants, nécessitant une analyse approfondie des donné
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Conference papers on the topic "Modèle CFD Code_Saturne"

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Song, Yuting, Xiangyu Yun, Tian Chen, Huiyong Zhang, Jiesheng Min, and Guofei Chen. "Investigation on Gas Dispersion Inside the Large-Scale Containment by CFD Simulation With Code_Saturne for Experimental Scenario Definition." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67027.

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During accidental situations, large quantities of hydrogen are generated and released due to metal-water reaction. Eventual stratification formed in the top region of containment and locally high concentration threatens the integrity of nuclear power plants. The stratification of hydrogen may be eroded by several measures, such as air jet, spray, ventilation. So far, several activities have been carried out on the hydrogen stratification’s break-up study. The well-known OECD/SETH-2 project used PANDA and MISTRA test facilities to study this phenomenon with variable test conditions. These test
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Fournier, Yvan, Sofiane Benhamadouche, David Monfort, and Dominique Laurence. "Non Conforming Meshes and RANS/LES Coupling: Two Challenging Aims for a CFD Code." In ASME 2004 Heat Transfer/Fluids Engineering Summer Conference. ASMEDC, 2004. http://dx.doi.org/10.1115/ht-fed2004-56340.

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This paper focuses on the geometry/solver interface for the CFD Software Code_Saturne ® which has been developed by EDF R&D since 1997 to replace its FE and BFC solvers. The solver includes various RANS models, as well as LES features and is parallelized through a domain splitting technique. It is based on a cell centered unstructured finite volume scheme, and accepts cells of any shape. This opened the possibility of using non conforming meshes, making it easier to build meshes with well-controlled quality and refinement even for complex geometries. Adjacent boundary faces of non-conformi
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Liu, Jiawei, Puzhen Gao, Tingting Xu, Jiesheng Min, and Guofei Chen. "Numerical Simulation of Flow Field Inside Reactor Upper Plenum for PWR With Code_Saturne." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-68008.

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Flow characteristic in upper plenum has a strong influence on reactor functional margin and rod cluster control assembly (RCCA) guide tube wear. Upper plenum flow governs loops flow rate measurement via hot leg temperature which has also an influence on the reactor protection system. For RCCA guide tube wear, it appears in operation with RCCA flow-induced vibration, leading to its replacement. It is important to know the flow condition in the upper plenum, and in particular the outlet. Existing Generation III reactors have their own specialties on the design. Comparison between current technol
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Natchez, Sebastien, Romain Ceyrolle, Vincent Loizeau, and Hervé Cordier. "CFD Modeling of a Full Clogging Event in a Pumping Station With Neptune_cfd Solver: A Preliminary Investigation." In 2024 31st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/icone31-135781.

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Abstract The drum screen filters the water upstream of the pumping station of a NPP to protect it from debris entrance. These devices can be damaged in case of full clogging events because of drum deformation or air aspiration in the pumps located downstream of the filter. With climate change and the contingency to face more clogging events, EDF has lately tried to estimate their impact on pumping stations by different manners. The focus was set on passive filtration (static filter with no cleaning system) to reduce the complexity of the modelling and the objective is to determine how long it
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Li, Jingya, and Xiaoying Zhang. "CFD Simulation of Passive Containment Cooling System in Hot Leg SB-LOCA for 1000MW PWR." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66025.

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The passive cooling system (PCCS) for reactor containment is a security system that can be used to cool the atmosphere and reduce pressure inside of containment in case of temperature and pressure increase caused by vapor injection, which requires no external power because it works only with natural forces. However, as the driving forces from natural physical phenomena are of low amplitude, uncertainties and instabilities in the physical process can cause failure of the system. This article aims to establish a CFD simulation model for the Passive Containment Cooling System of 1000MW PWR using
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Shams, Afaque, Nicolas Edh, and Kristian Angele. "Synthesis of a CFD Benchmark for the Thermal Mixing in a Sharp Corner T-Junction With a Wall." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81024.

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This article reports a CFD-benchmark with the purpose of validating different turbulence modelling approaches for the transient heat transfer due to mixing of hot and cold flow in a T-junction including the wall. This validation exercise has been carried out within the MOTHER project. In the framework of the project, new experiments were performed with a novel measurement sensor allowing the measurements of the fluctuating wall temperature inside the solid pipe wall. The tests were performed for two different Reynolds numbers (Re) 40000 and 60000 and for two different T-junction geometries; a
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Keshmiri, Amir, Mark A. Cotton, Yacine Addad, Stefano Rolfo, and Flavien Billard. "RANS and LES Investigations of Vertical Flows in the Fuel Passages of Gas-Cooled Nuclear Reactors." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48372.

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Coolant flows in the cores of current gas-cooled nuclear reactors consist of ascending vertical flows in a large number of parallel passages. Under post-trip conditions such heated turbulent flows may be significantly modified from the forced convection condition by the action of buoyancy, and the thermal-hydraulic regime is no longer one of pure forced convection. These modifications are primarily associated with changes to the turbulence structure, and indeed flow laminarization may occur. In the laminarization situation heat transfer rates may be as low as 40% of those in the corresponding
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Jusserand, Franc¸ois, Andre´ Adobes та Tseheno N. Randrianarivelo. "Solving U-RANS k-ω SST Equations and Post-Processing Motion Independent Fluid Forces in a Tube Bundle". У ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77691.

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The computation of the dynamic response of a structure subjected to a fluid flow requires the knowledge of the fluid forces acting on the structure. At least three classes of these forces can be distinguished: - fluid-elastic forces due to the coupling between fluid flow and structure displacement; - random forces due to the turbulent nature of the flow. In cases of two-phase fluid configurations, such as those occurring in steam generators of nuclear power plants, forces due to the two-phase nature of the fluid are also assumed to be part of this type of excitations; - fluid forces due to coh
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Berland, Julien, Enrico Deri, and André Adobes. "A Numerical Investigation of the Fluidelastic Coupling for a Cell of Flexible Tubes in a Square-in-Line Bundle Subject to Water Cross-Flow." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45097.

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The unsteady flow motions and the force distribution in a normal square tube array subject to cross-flow induced vibrations are investigated by means of large-eddy simulations. The flow configuration and the operating conditions are taken from the experiments of Gosse et al. (PVP Conference, 2001). The set-up is made of 63 (9 rows and 7 columns) straight tube bundle. The tubes are arranged in a square in line pattern, and a cell of 9 flexible tubes, located in the middle of the bundle, may translate in the drag and lift directions. The LES of cross-flow induced vibrations of a cell of 9 flexib
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