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

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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Bibliographic Details
Main Authors: Stephane Mimouni, William Benguigui, Solène Fleau, Arnaud Foissac, Mathieu Guingo, Mickael Hassanaly, Jérôme Lavieville, Jeanne Malet, Namane Méchitoua, Nicolas Mérigoux, Stéphane Vincent
Format: Article
Language:English
Published: Hindawi Limited 2017-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2017/3238545

Internet

http://dx.doi.org/10.1155/2017/3238545

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