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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Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2009/950536 |
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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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