Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code

Two-dimensional axisymmetric simulations of pressurized thermal shock (PTS) phenomena through Neptune_CFD module are presented aiming at two-phase models validation against experimental data. Because of PTS complexity, only some thermal-hydraulic aspects were considered. Two different flow configura...

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Main Authors: Maria Cristina Galassi, Pierre Coste, Christophe Morel, Fabio Moretti
Format: Article
Language:English
Published: Hindawi Limited 2009-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2009/950536
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spelling doaj-c57310825908414eb0426dcc9e269bb02020-11-24T23:54:33ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832009-01-01200910.1155/2009/950536950536Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD CodeMaria Cristina Galassi0Pierre Coste1Christophe Morel2Fabio Moretti3Department of Mechanical, Nuclear, and Production Engineering (DIMNP), University of Pisa, Via Diotisalvi n. 2, 56126 Pisa, ItalyDEN/DER/SSTH/LMDL, CEA/Grenoble, 17 Rue des Martyrs, 38054 Grenoble Cedex 9, FranceDEN/DER/SSTH/LMDL, CEA/Grenoble, 17 Rue des Martyrs, 38054 Grenoble Cedex 9, FranceDepartment of Mechanical, Nuclear, and Production Engineering (DIMNP), University of Pisa, Via Diotisalvi n. 2, 56126 Pisa, ItalyTwo-dimensional axisymmetric simulations of pressurized thermal shock (PTS) phenomena through Neptune_CFD module are presented aiming at two-phase models validation against experimental data. Because of PTS complexity, only some thermal-hydraulic aspects were considered. Two different flow configurations were studied, occurring when emergency core cooling (ECC) water is injected in an uncovered cold leg of a pressurized water reactor (PWR)—a plunging water jet entering a free surface, and a stratified steam-water flow. Some standard and new implemented models were tested: modified turbulent 𝑘-𝜀 models with turbulence production induced by interfacial friction, models for the drag coefficient, and interfacial heat transfer models. Quite good agreement with experimental data was achieved with best performing models for both test cases, even if a further improvement in phase change modelling would be suitable for nuclear technology applications.http://dx.doi.org/10.1155/2009/950536
collection DOAJ
language English
format Article
sources DOAJ
author Maria Cristina Galassi
Pierre Coste
Christophe Morel
Fabio Moretti
spellingShingle Maria Cristina Galassi
Pierre Coste
Christophe Morel
Fabio Moretti
Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
Science and Technology of Nuclear Installations
author_facet Maria Cristina Galassi
Pierre Coste
Christophe Morel
Fabio Moretti
author_sort Maria Cristina Galassi
title Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
title_short Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
title_full Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
title_fullStr Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
title_full_unstemmed Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
title_sort two-phase flow simulations for pts investigation by means of neptune_cfd code
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2009-01-01
description Two-dimensional axisymmetric simulations of pressurized thermal shock (PTS) phenomena through Neptune_CFD module are presented aiming at two-phase models validation against experimental data. Because of PTS complexity, only some thermal-hydraulic aspects were considered. Two different flow configurations were studied, occurring when emergency core cooling (ECC) water is injected in an uncovered cold leg of a pressurized water reactor (PWR)—a plunging water jet entering a free surface, and a stratified steam-water flow. Some standard and new implemented models were tested: modified turbulent 𝑘-𝜀 models with turbulence production induced by interfacial friction, models for the drag coefficient, and interfacial heat transfer models. Quite good agreement with experimental data was achieved with best performing models for both test cases, even if a further improvement in phase change modelling would be suitable for nuclear technology applications.
url http://dx.doi.org/10.1155/2009/950536
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