Modelling and computation of cavitation and boiling bubbly flows with the NEPTUNE_CFD code

Mimouni, S.; Boucker, M.; Laviéville, Jérôme; Guelfi, Antoine; Bestion, D.

doi:10.1016/j.nucengdes.2007.02.052

Cited by 69 publications

(32 citation statements)

References 10 publications

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“…Given all this, the basic heat flux partitioning model cannot be used under critical heat flux conditions. In order to take into account the phenomenon of temperature excursion at DNB conditions, the heat flux partitioning model has been generalized by adding a fourth part of the wall heat flux, V , diffusive heat flux used to superheat the gas phase [37] (Mimouni, 2010):…”

Section: Standard Wall Transfer Model For Nucleate Boilingmentioning

confidence: 99%

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Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code

Mimouni

Benguigui

Fleau

et al. 2017

Science and Technology of Nuclear Installations

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The objective of this paper is to give an overview of the capabilities of Eulerian bifluid approach to meet the needs of studies for nuclear safety regarding hydrogen risk, boiling crisis, and pipes and valves maintenance. The Eulerian bifluid approach has been implemented in a CFD code named NEPTUNE CFD. NEPTUNE CFD is a three-dimensional multifluid code developed especially for nuclear reactor applications by EDF, CEA, AREVA, and IRSN. The first set of models is dedicated to wall vapor condensation and spray modelling. Moreover, boiling crisis remains a major limiting phenomenon for the analysis of operation and safety of both nuclear reactors and conventional thermal power systems. The paper aims at presenting the generalization of the previous DNB model and its validation against 1500 validation cases. The modelling and the numerical simulation of cavitation phenomena are of relevant interest in many industrial applications, especially regarding pipes and valves maintenance where cavitating flows are responsible for harmful acoustics effects. In the last section, models are validated against experimental data of pressure profiles and void fraction visualisations obtained downstream of an orifice with the EPOCA facility (EDF R&D). Finally, a multifield approach is presented as an efficient tool to run all models together.

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Section: Standard Wall Transfer Model For Nucleate Boilingmentioning

confidence: 99%

“…The same process is applied to the liquid velocity [37]. Moreover, if the liquid temperature in the nearest cell at the wall tends to the saturation temperature, then the single-phase-flow convective heat flux tends to 0, and the corresponding energy contributes to the vaporisation heat flux.…”

Section: Standard Wall Transfer Model For Nucleate Boilingmentioning

confidence: 99%

Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code

Mimouni

Benguigui

Fleau

et al. 2017

Science and Technology of Nuclear Installations

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“…In the latter case, d g represents the Sauter mean diameter of a size spectrum. [4] Five CFX 4.2 prescribed number density [6] Four CFX 4.2 additional transport equation for number density [7] Six FLUENT 6.2.16 additional transport equation for number density [8] Six NEPTUNE_CFD prescribed size [9] Five CFX 14.5 additional transport equation for number density…”

Section: Interfacial Area Densitymentioning

confidence: 99%

Possibilities and Limitations of CFD Simulation for Flashing Flow Scenarios in Nuclear Applications

Liao

Lucas

2017

Energies

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Abstract:The flashing phenomenon is relevant to nuclear safety analysis, for example by a loss of coolant accident and safety release scenarios. It has been studied intensively by means of experiments and simulations with system codes, but computational fluid dynamics (CFD) simulation is still at the embryonic stage. Rapid increasing computer speed makes it possible to apply the CFD technology in such complex flow situations. Nevertheless, a thorough evaluation on the limitations and restrictions is still missing, which is however indispensable for reliable application, as well as further development. In the present work, the commonly-used two-fluid model with different mono-disperse assumptions is used to simulate various flashing scenarios. With the help of available experimental data, the results are evaluated, and the limitations are discussed. A poly-disperse method is found necessary for a reliable prediction of mean bubble size and phase distribution. The first attempts to trace the evolution of the bubble size distribution by means of poly-disperse simulations are made.

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“…: a continuous liquid field, a dispersed liquid field, a continuous vapour field, a dispersed vapour field). The solver is implemented in the NEPTUNE software environment (Guelfi, 2007), (Mimouni, 2007(Mimouni, , 2008, which is based on a finite volume discretization, together with a collocated arrangement for all variables. The data structure is totally face-based which allows the use of arbitrary shaped cells (tetraedra, hexaedra, prisms, pyramids ...) including non conforming meshes.…”

Section: Introductionmentioning

confidence: 99%