31st ETPFGM 1993
Hannover, 7 - 10 June 1993
Organiser: D. Mewes
List of papers presented
Heat Transfer Behaviour of a SACO with Gravity Feed
W. Kohler, O. Herbst and W. Kastner
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International Standard Problems ISP-33 at PACTEL Facility for the Simulation of VVER-440 Type PWRs
J. Kouhia, J. Tuunanen and T. Kervinen
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A Single Stage High Pressure Steam Injector for Next Generation Reactors: Test Results and Analysis
L. Galbiati, G. Cattadori, L. Mazzocchi and P. Vanini
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UPTF Experiment: Flow Phenomena During Full-Scale Loop Seal Clearing of a PWR
J. Liebert, R. Emmerling and P. Weiss
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UPTF Experiment: TRAM - Flow Patterns and Water Transport Mechanism in a PWR Hot Leg Under Two-Phase Natural Circulation Conditions
W. Junghans, R. Emmerling and P. Weiss
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Pressure Drop and Liquid Content in a C02 Two-Phase Pipeline Network with Outlet Nozzles Under Critical Conditions. Calculation and Experimental Verification
P. Gebhard, G. Kiederle and F. Mayinger
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Dropwise Condensation of Air-Steam Mixtures in a Compact Heat Exchanger
C.W.M. van der Geld and J. Bronwers
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An Initial Investigation into Phase Maldistribution in Evaporators
D.A. McNeal
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Two-Phase Pressure Drop Across Sudden Flow Cross-Section Contractions
J. Schmidt and L. Friedel
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Droplet Size and Velocity at the Exit of a Nozzle With Two-Component Critical Flow
H. Lemonnier and E. Camelo
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A Six Equation Model According to SFAV-Approach with Correct Propagating Velocities of Disturbances
M. Rajamaki and T. Narumo
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Use of the CATHARE 1D Pump Model to Predict the Two-Phase Characteristic of a Pump for Petroleum Fluids
P. Coste and R. Vilagines
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MONA, a 7-Equation Transient Two-Phase Flow Model for LWR Dynamics
J. Rasmussen and N. Hoyer
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Simulation of the Behaviour of a Typical PWR Steam Generator by Means of the RELAP5/Mod 3 Nuclear Plant Analyzer
Y. Crommelynck, E.J Stubbe and L. Vanhoenacker
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Critical Heat Flux Tests in Circular Tubes
U. Müller and F.J. Erbacher
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Measurement of Local Thermal Hydraulic Parameters in R12 Simulating PWR Conditions From One Phase Flow Until Critical Heat Flux Conditions
J. Garnier
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Analysis of in-R12 CHF Data: Influence of Hydraulic and Heating Diameters and Heating Length, Test of Theoretical Boiling Crisis Models
J.Y. Olive, A. Souyri, V. Czop, J. Garnier and Ch. Herer
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Comparison of CHF Predictors Obtained by the Pseudo-Cubic Spline Method from FLICA-3M and EDF's THYC Computations
D. Banner and F. De Crecy
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Predictions of CHF in Subcooled Flow Boiling at High Liquid Velocity and Subcooling
G.P. Celata, M. Cumo and A. Mariani
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FC, the Framatome Correlation for Critical Heat Flux in Pressurized Water Reactor Rod Bundles
R. Aved and J.P. Bourteele
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The Research Program on the Instability of Boiling Channels to be Carried Out by Piper-One Apparatus
W. Ambrosini, F. D'Auria, G. Galassi and M. Mazzini
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Direct Contact Boiling of Immiscible Liquids
G.P. Celata, M. Cumo and F. D'Annibale
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Liquid Layer and Wall Shear Stress Characteristics in Stratified/Atomization Flow
A.J. Karabelas, N Vlachos and S.V. Paras
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Two-Phase Flow Patterns During Evaporation of the New Refrigerants in Tubes and Annuli
J R. Thome, N. Kattan and D. Favrat
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Search for Correlations by Artificial Neural Network Approach: Two-Phase Thermohydraulic Study Case
C. Lombardi, E. Zio, M. Marseguerra and E. Ricotti
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Aspects of Three-Phase Flows in Gas Condensate Pipelines
K. Lunde, S. Nuland and M. Lingelem
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Multiphase Slug Flow in Horizontal Pipes
M. Nädler and D. Mewes
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Horizontal Slug Flow: Development in Long Pipe
J. Fabre, E. Gadoin, Ph. Grenier and A. Line
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Transient Simulation of Two-Phase Hydrocarbon Flows in Pipelines
A.R.W. Hall and G.R. Butcher