OECD International Standard Problem ISP-47 on containment thermal-hydraulics—Conclusions of the TOSQAN part

Malet, J.; Porcheron, Emmanuel; Vendel, J.

doi:10.1016/j.nucengdes.2010.05.061

Cited by 72 publications

(20 citation statements)

References 2 publications

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“…3: results are given for the steady-states of the wall condensation tests, for all 8 tests of Table 1 and for one more test to illustrate the repeatability. More information the good repeatability of wall condensation TOSQAN tests can be found in Malet et al (2010). The agreement is good, indicating that steady-state thermodynamics is well calculated in these simulations.…”

Section: Results During Wall Condensation Steady-statessupporting

confidence: 57%

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Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident

Malet¹,

Gélain²

2014

Progress in Nuclear Energy

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Section: Results During Wall Condensation Steady-statessupporting

confidence: 57%

“…This facility has a lot of specific instrumentation implemented with a high density in relation to its size. It has already been improved for containment code validation on atmosphere containment mixing by convection and wall condensation (Malet et al 2010;Mimouni et al, 2011).…”

Section: Introductionmentioning

confidence: 99%

Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident

Malet¹,

Gélain²

2014

Progress in Nuclear Energy

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“…It is of relevant interest to be able to propose and validate several approaches. Indeed, this strategy allows improving the reliability of the results in the simulation of realistic scenarios, such as in TOSQAN ISP-47 [1].…”

Section: Science and Technology Of Nuclear Installationsmentioning

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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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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“…Recently, Vyskocil et al [6], Zschaeck et al [7], and Dehbi et al [1] analyzed wall condensation heat transfer and an air-steam mixture for containment application using commercial CFDs, ANSYS-CFX (ANSYS Inc., Canonsburg, PA, USA) and FLUENT (ANSYS Inc.). The local diffusion approach was applied and the performance of the condensation models was tested on various experimental databases, such as CONAN test [4], PANDA [8], Kuhn test [9], COPAIN [10], TOSQAN [11], and on experimental models devised by Uchida et al [12], Tagami [13], Dehbi et al [14], and so on. Dehbi [2] simulated wall film condensation in the presence of noncondensable gases using ANSYS FLUENT and investigated the effect of near-wall mesh resolution on CFD predictions.…”

Section: Introductionmentioning

confidence: 99%

“…Mimouni et al [16,17] proposed a wall condensation model for NEPTUNE-CFD which incorporates the two-fluid model for its governing equations and the condensation rate was estimated using the heat and mass transfer analogy approach. The model was validated against experimental data provided by TOSQAN [11] and COPAIN [10]. Meanwhile, a commercial CFD code, STAR-CCMþ [18], provides the wall condensation simulation with a thin liquid film using the fluid-film model.…”

Section: Introductionmentioning

confidence: 99%

Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases

Lee

Park

Cho

2015

Nuclear Engineering and Technology

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a b s t r a c tIn a nuclear reactor containment, wall condensation forms with noncondensable gases and their accumulation near the condensate film leads to a significant reduction in heat transfer. In the framework of nuclear reactor safety, the film condensation in the presence of noncondensable gases is of high relevance with regards to safety concerns as it is closely associated with peak pressure predictions for containment integrity and the performance of components installed for containment cooling in accident conditions. In the present study, CUPID code, which has been developed by KAERI for the analysis of transient twophase flows in nuclear reactor components, is improved for simulating film condensation in the presence of noncondensable gases. In order to evaluate the condensate heat transfer accurately in a large system using the two-fluid model, a mass diffusion model, a liquid film model, and a wall film condensation model were implemented into CUPID. For the condensation simulation, a wall function approach with a heat/mass transfer analogy was applied in order to save computational time without considerable refinement for the boundary layer. This paper presents the implemented wall film condensation model, and then introduces the simulation result using the improved CUPID for a conceptual condensation problem in a large system.

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OECD International Standard Problem ISP-47 on containment thermal-hydraulics—Conclusions of the TOSQAN part

Cited by 72 publications

References 2 publications

Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident

Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident

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

Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases

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