TY - JOUR
T1 - Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE-CFD Code
AU - Mimouni, Stephane
AU - Benguigui, William
AU - Fleau, Solène
AU - Foissac, Arnaud
AU - Guingo, Mathieu
AU - Hassanaly, Mickael
AU - Lavieville, Jérôme
AU - Malet, Jeanne
AU - Méchitoua, Namane
AU - Mérigoux, Nicolas
AU - Vincent, Stéphane
N1 - Publisher Copyright:
© 2017 Stephane Mimouni et al.
PY - 2017/1/1
Y1 - 2017/1/1
N2 - 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.
AB - 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.
U2 - 10.1155/2017/3238545
DO - 10.1155/2017/3238545
M3 - Article
AN - SCOPUS:85042707300
SN - 1687-6075
VL - 2017
JO - Science and Technology of Nuclear Installations
JF - Science and Technology of Nuclear Installations
M1 - 3238545
ER -