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: | Stephane Mimouni, William Benguigui, Solène Fleau, Arnaud Foissac, Mathieu Guingo, Mickael Hassanaly, Jérôme Lavieville, Jeanne Malet, Namane Méchitoua, Nicolas Mérigoux, Stéphane Vincent |
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| Format: | Article |
| Language: | English |
| Published: |
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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