Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code
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 NEPTUN...
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| Main Authors: | , , , , , , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/3238545 |
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| author | Stephane Mimouni William Benguigui Solène Fleau Arnaud Foissac Mathieu Guingo Mickael Hassanaly Jérôme Lavieville Jeanne Malet Namane Méchitoua Nicolas Mérigoux Stéphane Vincent |
| author_facet | Stephane Mimouni William Benguigui Solène Fleau Arnaud Foissac Mathieu Guingo Mickael Hassanaly Jérôme Lavieville Jeanne Malet Namane Méchitoua Nicolas Mérigoux Stéphane Vincent |
| author_sort | Stephane Mimouni |
| collection | DOAJ |
| description | 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. |
| format | Article |
| id | doaj-art-1d2c15de060a446d8ae8dd08310d8b43 |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-1d2c15de060a446d8ae8dd08310d8b432025-08-20T02:01:43ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/32385453238545Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD CodeStephane Mimouni0William Benguigui1Solène Fleau2Arnaud Foissac3Mathieu Guingo4Mickael Hassanaly5Jérôme Lavieville6Jeanne Malet7Namane Méchitoua8Nicolas Mérigoux9Stéphane Vincent10R&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceInstitut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, SCA, 91192 Gif-sur-Yvette, FranceR&D Division, Electricité de France, 78400 Chatou, FranceR&D Division, Electricité de France, 78400 Chatou, FranceLaboratoire Modélisation et Simulation Multi Echelle (MSME), UMR CNRS 8208, Université Paris-Est Marne-la-Vallée, 77454 Marne-la-Vallée, FranceThe 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.http://dx.doi.org/10.1155/2017/3238545 |
| spellingShingle | Stephane Mimouni William Benguigui Solène Fleau Arnaud Foissac Mathieu Guingo Mickael Hassanaly Jérôme Lavieville Jeanne Malet Namane Méchitoua Nicolas Mérigoux Stéphane Vincent Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code Science and Technology of Nuclear Installations |
| title | Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code |
| title_full | Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code |
| title_fullStr | Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code |
| title_full_unstemmed | Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code |
| title_short | Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code |
| title_sort | dispersed two phase flow modelling for nuclear safety in the neptune cfd code |
| url | http://dx.doi.org/10.1155/2017/3238545 |
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