Two-phase flow simulations for PTS investigation by means of neptune-CFD code

Science and Technology of Nuclear Installations

Volumn 2009, Issue , 2009, Pages

  Galassi, Maria Cristina ^a   Coste, Pierre ^b   Morel, Christophe ^b   Moretti, Fabio ^a  

^a UNIVERSITY OF PISA   (Italy)

^b CEA GRENOBLE   (France)

Author keywords

[No Author keywords available]

Indexed keywords

AXISYMMETRIC SIMULATION; FLOW CONFIGURATIONS; INTERFACIAL FRICTION; INTERFACIAL HEAT TRANSFER; NUCLEAR TECHNOLOGY; PRESSURIZED THERMAL SHOCK; THERMAL HYDRAULICS; TURBULENCE PRODUCTIONS;

COMPUTATIONAL FLUID DYNAMICS; PRESSURIZED WATER REACTORS;

COMPUTER SIMULATION;

EID: 84859375838     PISSN: 16876075     EISSN: 16876083     Source Type: Journal    
DOI: 10.1155/2009/950536     Document Type: Article

References (25)

1. Guelfi A., Boucker M., Hérard J. M., A new multi-scale platform for advanced nuclear thermal-hydraulics status and prospects of the NEPTUNE project. Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 11) October 2005 Avignon, France
2. Bestion D., Guelfi A., Status and perspective of two-phase flow modelling in the NEPTUNE multi-scale thermal-hydraulic platform for nuclear reactor simulation. Nuclear Engineering and Technology 2005 37 6
3. Guelfi A., antoine.guelfi@edf.fr Bestion D., Boucker M., NEPTUNE: a new software platform for advanced nuclear thermal hydraulics. Nuclear Science and Engineering 2007 156 3 281 324 (Pubitemid 47158095)
4. Méchitoua N., Boucker M., Laviéville J., Hérard J., Pigny S., Serre G., An unstructured finite volume solver for two-phase water-vapour flows based on an elliptic oriented fractional step method. Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 11) October 2005 Avignon, France
5. Laviéville J., Quémérais E., Mimouni S., Méchitoua N.,. NEPTUNE CFD V1.0 theory manual, EDF, 2006
6. Laviéville J., Quémérais E., Boucker M., Maas L.,. NEPTUNE CFD V1.0 User Guide, EDF, 2005
7. Riikonen V., Ilvonen M., Lucas D., Deliverable D2.1.1: identification of relevant PTS-scenarios, state of the art of modelling and needs for model improvement. European Commission 6th Euratom Framework Programme 2005-2008, Integrated Project (IP): NURESIM, Nuclear Reactor Simulations, Sub-Project 2: Thermal Hydraulics 2006 27 34
8. Vihavainen J., Puustinen M., Lucas D., Deliverable D2.1.2: review of the existing data basis for the validation of models for PTS. European Commission 6th Euratom framework programme 2005-2008, Integrated Project (IP): NURESIM, Nuclear Reactor Simulations, Sub-Project 2: Thermal Hydraulics 2006 51 58
9. Scheuerer M., Menter F., Egorov Y., Selection of PTS-relevant test cases. 5th Euratom Framework Programme 1998-2002, EVOL-ECORA-D05a, December 2002
10. Egorov Y., Boucker M., Martin A., Pigny S., Scheuerer M., Willemsen S., Validation of CFD codes with PTS-relevant test cases. 5th Euratom Framework Programme 1998-2002, EVOL-ECORA-D07, September 2004
11. Iguchi M., Okita K., Yamamoto F., Mean velocity and turbulence characteristics of water flow in the bubble dispersion region induced by plunging water jet. International Journal of Multiphase Flow 1998 24 4 523 537 10.1016/S0301-9322(97)00084-0 (Pubitemid 28444326)
12. Ruile H., Direktkontaktkondensation in geschichteten Zweiphasenströ mungen [thesis] 1996 Düsseldorf, Germany VDI Verlag
13. Hein D., Ruile H., Karl J.,. Kühlmittelerwärmung bei Direktkontaktkondensation an horizontalen Schichten und vertikalen Streifen zur Quantifizierung des druckbelasteten Thermoschocks, BMFT Forschungsvorhaben 1500906, Abschlußericht, Lehrstuhl für Thermische Kraftanlagen, TU München, 1995
14. Goldbrunner M., Karl J., Hein D., Experimental investigation of heat transfer phenomena during direct contact condensation in the presence of non condensable gas by means of linear raman spectroscopy. Proceedings of the 10th International Symposium on Applications of Laser Techniques to Fluid Mechanics July 2000 Lisbon, Portugal
15. Ishii M., Thermo-Fluid Dynamic Theory of Two-Phase Flow 1975 Paris, France Eyrolles Collection de la Direction des Etudes et Recherches d'Electricite de France, no. 22
16. Morel C., Mimouni S., Laviéville J. M., Boucker M., R113 boiling bubbly flow in an annular geometry simulated with the NEPTUNE code. Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 11) October 2005 Avignon, France
17. Yao W., Bestion D., dominique.bestion@cea.fr Coste P., Boucker M., A three-dimensional two-fluid modeling of stratified flow with condensation for pressurized thermal shock investigations. Nuclear Technology 2005 152 1 129 142 (Pubitemid 41320437)
18. Ferziger J. H., Peric M., Computational Method for Fluid Dynamics 2002 3rd Berlin, Germany Springer
19. Boucker M., marc.boucker@edf.fr Laviéville J., jerome-marcel.lavieville@edf.fr Martin A., alain-cc.martin@edf.fr Béchaud C., celine.bechaud@edf.fr Bestion D., dominique.bestion@cea.fr Coste P., pierre.coste@cea.fr Preliminary applications of the new NEPTUNE two-phase CFD solver to pressurized thermal shock investigations. 2 Proceedings of the 12th International Conference on Nuclear Engineering (ICONE '04) April 2004 Arlington, Va, USA 745 751
20. Higbie R., The rate of absorption of a pure gas into a still liquid during a short time of exposure. Transactions of the American Institute of Chemical Engineers 1935 31 365 389
21. Coste P., Computational simulation of multi-D liquid-vapour thermal shock with condensation. Proceedings of the 5th International Conference on Multiphase Flow (ICMF '04) May-June 2004 Yokohama, Japan
22. Kondo S., Tobita Y., Morita K., Shirakawa N., SIMMER-III: an advanced computer program for LMFBR severe accident analysis. Proceedings of the International Conference on Design and Safety of Advanced Nuclear Power Plants (ANP '92) October 1992 Tokyo, Japan
23. Coste P., An approach of multidimensional condensation modeling for ECC injection. Proceedings of the 41st European Two-Phase Flow Group Meeting May 2003 Trondheim, Norway
24. Coste P., Pouvreau J., Morel C., Laviéville J., Boucker M., Martin A., Modeling turbulence and friction around a large interface in a three-dimension two-velocity Eulerian code. Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 12) September-October 2007 Pittsburgh, Pa, USA
25. Galassi M. C., mc.galassi@ing.unipi.it Morel C., christophe.morel@cea.fr Bestion D., dominique.bestion@cea.fr Pouvreau J., jerome.pouvreau@cea.fr D'Auria F., f.dauria@ing.unipi.it Validation of NEPTUNE CFD module with data of a plunging water jet entering a free surface. Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 12) September-October 2007 Pittsburgh, Pa, USA