Multiscale analysis of nuclear reactors Thermal-hydraulics - : the Neptune project : Progrès des méthodes de modélisation des écoulements diphasiquesBESTION, Dominique; GUELFI, Antoine.Houille blanche (Grenoble). 2005, Num 5, issn 0018-6368, 3, 65-74 [11 p.]Conference Paper

Study of release of nitrogen gas dissolved in water during depressurisation-application to primary circuit of pwrSARRETTE, Christine; BESTION, Dominique.Nuclear engineering and design. 2003, Vol 224, Num 3, pp 337-358, issn 0029-5493, 22 p.Article

Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off modelBAE, Byoung-Uhn; YUN, Byong-Jo; YOON, Han-Young et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2281-2294, issn 0029-5493, 14 p.Conference Paper

CFD-modeling of insulation debris transport phenomena in water flowKREPPER, Eckhard; CARTLAND-GLOVER, Gregory; GRAHN, Alexander et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2357-2364, issn 0029-5493, 8 p.Conference Paper

A CFD simulation process for fast reactor fuel assembliesHAMMAN, Kurt D; BERRY, Ray A.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2304-2312, issn 0029-5493, 9 p.Conference Paper

Fluid-structure interaction analysis of large-break loss of coolant accidentBRANDT, Tellervo; LESTINEN, Ville; TOPPILA, Timo et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2365-2374, issn 0029-5493, 10 p.Conference Paper

Revisiting large break LOCA with the CATHARE-3 three-field modelVALETTE, Michel; POUVREAU, Jérôme; BESTION, Dominique et al.Nuclear engineering and design. 2011, Vol 241, Num 11, pp 4487-4496, issn 0029-5493, 10 p.Article

Benchmark database on the evolution of two-phase flows in a vertical pipeLUCAS, D; BEYER, M; KUSSIN, J et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2338-2346, issn 0029-5493, 9 p.Conference Paper

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulusYUN, B. J; BAE, B. U; EUH, D. J et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2295-2303, issn 0029-5493, 9 p.Conference Paper

Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modelingKLIEM, S; HÖHNE, T; ROHDE, U et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2271-2280, issn 0029-5493, 10 p.Conference Paper

Flow measurement techniques in heavy liquid metalsSCHULENBERG, Thomas; STIEGLITZ, Robert.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2077-2087, issn 0029-5493, 11 p.Conference Paper

Fluent analysis of a ROSA cold leg stratification testFARKAS, T; TOTH, I.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2169-2175, issn 0029-5493, 7 p.Conference Paper

NEPTUNE : A new software platform for advanced nuclear thermal hydraulicsGUELFI, Antoine; BESTION, Dominique; BOUCKER, Marc et al.Nuclear science and engineering. 2007, Vol 156, Num 3, pp 281-324, issn 0029-5639, 44 p.Article

Experiments and CFD Code Applications to Nuclear Reactor Safety (XCFD4NRS)SMITH, Brian L; BESTION, Dominique; HASSAN, Yassin et al.Nuclear engineering and design. 2010, Vol 240, Num 9, issn 0029-5493, 311 p.Conference Proceedings

CFD study on coolant mixing in VVER-440 fuel rod bundles and fuel assembly headsTOTH, S; ASZODI, A.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2194-2205, issn 0029-5493, 12 p.Conference Paper

Experimental CFD grade data for stratified two-phase flowsVALLEE, Christophe; LUCAS, Dirk; BEYER, Matthias et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2347-2356, issn 0029-5493, 10 p.Conference Paper

Large-Eddy Simulation study of turbulent mixing in a T-junctionKUCZAJ, A. K; KOMEN, E. M. J; LOGINOV, M. S et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2116-2122, issn 0029-5493, 7 p.Conference Paper

Modelling of sprays in containment applications with A CMFD codeMIMOUNI, S; LAMY, J.-S; LAVIEVILLE, J et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2260-2270, issn 0029-5493, 11 p.Conference Paper

PIV measurements of turbulent jet and pool mixing produced by a steam jet discharge in a subcooled water poolYEON JUN CHOO; SONG, Chul-Hwa.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2215-2224, issn 0029-5493, 10 p.Conference Paper

Towards a multi-scale approach of two-phase flow modeling in the context of DNB modelingJAMET, D; LEBAIGUE, O; MOREL, C et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2131-2138, issn 0029-5493, 8 p.Conference Paper

NURESIM: A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysisCHAULIAC, Christian; ARAGONES, José-Maria; BESTION, Dominique et al.Nuclear engineering and design. 2011, Vol 241, Num 9, pp 3416-3426, issn 0029-5493, 11 p.Conference Paper

An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower headTRAN, C. T; KUDINOV, P; DINH, T. N et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2148-2159, issn 0029-5493, 12 p.Conference Paper

LEIS for the prediction of turbulent multifluid flows applied to thermal-hydraulics applicationsLAKEHAL, Djamel.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2096-2106, issn 0029-5493, 11 p.Conference Paper

Modeling and measurement of interfacial area concentration in two-phase flowPARANJAPE, Sidharth; ISHII, Mamoru; HIBIKI, Takashi et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2329-2337, issn 0029-5493, 9 p.Conference Paper

Simulation of a gas jet entering the secondary side of a steam generator during a SGTR sequence: Validation of a FLUENT 6.2 ModelLOPEZ DEL PRA, C; VELASCO, F. J. S; HERRANZ, L. E et al.Nuclear engineering and design. 2010, Vol 240, Num 9, pp 2206-2214, issn 0029-5493, 9 p.Conference Paper