Investigation of large-scale gas mixing and stratification phenomena related to LWR containment studies in the PANDA facility

Auban, Olivier; Zboray, Robert; Paladino, Domenico

doi:10.1016/j.nucengdes.2006.07.011

Cited by 55 publications

(22 citation statements)

References 4 publications

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“…More details on Test 17 are given in [11], which has however, limited distribution. The main features of the facility and of the instrumentation used for the experimental programme, as well as some aspects of Tests 9 and 17 are presented in [12,13]. For the sake of the present discussion, it is sufficient to say that the specifications for initial and boundary conditions were matched in both tests and accurate data could be collected.…”

Section: Comparison Of Resultsmentioning

confidence: 99%

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A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge

Andreani

Haller

Heitsch

et al. 2008

Nuclear Engineering and Design

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Section: Comparison Of Resultsmentioning

confidence: 99%

“…For the sake of the present discussion, it is sufficient to say that the specifications for initial and boundary conditions were matched in both tests and accurate data could be collected. It should be mentioned here that for Test 17 four repeat tests have been performed, with good repeatability, as discussed in [13].…”

Section: Comparison Of Resultsmentioning

confidence: 99%

A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge

Andreani

Haller

Heitsch

et al. 2008

Nuclear Engineering and Design

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“…PANDA and MISTRA are large-scale thermal-hydraulics test facilities designed and used for investigating containment related phenomena for different Light Water Reactors designs (Auban, 2007 and. Two main PANDA vessels (named Vessel 1 and 2) are used in the SETH-2 project to represent two compartments of a nuclear reactor containment.…”

Section: Facilities and Tests Conditionsmentioning

confidence: 99%

Interaction of a light gas stratified layer with an air jet coming from below: Large scale experiments and scaling issues

Studer

Brinster

Tkatschenko

et al. 2012

Nuclear Engineering and Design

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In the frame of the OECD/SETH-2 project, an experimental programme is being carried out in parallel in the PANDA facility at the Paul Scherrer Institute and in the MISTRA facility at the Commissariat à l'Energie Atomique. Part of the program focuses on gas stratification break-up induced by mass sources and similar tests have been performed in both facilities. Indeed, the scaling effect of the phenomena involved in the erosion of a gas stratified layer can be assessed. Depending on the interaction Froude number, different regimes have been identified including pure diffusive mixing, global dilution or slow erosion processes. These phenomena are driven by different time scales. Small value of the non-dimensional number leads to mixing process driven by molecular diffusion. When the interaction Froude number is increased to large values, the dilution process can be described by a global time scale based on volumetric mixing provided that the air entrainment by the jet is taken into account. The intermediate case with two layers is more complicated and a single time scale cannot be derived. These test results with high-quality measurements can be regarded as a good basis for CFD models verification.

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“…which is the formulation at the CFD scale of condensation properties experimentally observed at the droplet scale [19 [20]. Initially Vessel-1 presents an Air-He mixture layer at ambient temperature and pressure ( Figure 2).…”

Section: Mass Balance Equation Of the Noncondensable Gasmentioning

confidence: 93%

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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Investigation of large-scale gas mixing and stratification phenomena related to LWR containment studies in the PANDA facility

Cited by 55 publications

References 4 publications

A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge

A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge

Interaction of a light gas stratified layer with an air jet coming from below: Large scale experiments and scaling issues

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

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