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No. 1 (1993): Fourth International Conference on Simulation Methods in Nuclear Engineering
Published:
1993-06-04
Articles
Fine Nunerical Modelling of Thermohydraulic Phenomena in EdF PWR Reactors
F. Boulot
PDF
The Quest for Prototypical Conditions in the Phebus-FP Containment
I. Shepherd, A. Jones, P. Hardt, S. Gaillot
PDF
Direct Simulation of Multiphase Flows
S. Banerjee
PDF
Recent Developments in the CATHENA Two-Fluid Thermalhydraulics Code
B. Hanna, M. Lavack, N.U. Aydemir, H.M. Huynh, R. Girard
PDF
Transport/Diffusion Equivalence Method in the EdF Neutronic Calculation Scheme: Application to EPICURE Experiment Interpretation
C. Garzenne, J.C. Lefebvre
PDF
TUF Version Control and Development Status
W.S. Liu, T. Warne, A.P. Muzumdar, John C. Luxat
PDF
A Model for Computing Two-Phase Pressure Drop in Vertical U-Tube Steam Generators and its Application to Thermosyphoning
P. Gulshani, H. Huynh, P.D. Thompson
PDF
Modelling of RD-14M Partial-Inventory Thermosyphoning Tests Using the OHAT Code
P.T. Wan, W.I. Midvidy, John C. Luxat
PDF
A Homogeneous Non-Equilibrium Critical Flow Model for Leak Rate Predictions
K. Crentsil, S.I. Osamusali, R.Y. Chu
PDF
THYC-3D A Computer Code for Thermalhydraulic Analysis
M. Asok Kumar
PDF
An Inherently Parallel Multigroup Nodal Diffusion Method for Hexagonal-Z Geometry
A.M. Ougouag, W. Fitzpatrick
PDF
Kinetic Methods for the Diffusion Equations in Nuclear PWR
X. Warin
PDF
Detailed Reactor Analysis Code Simplifies MonteCarlo Transport Calculations
Bryan R. Lewis, Mark R. Steelman
PDF
A Discrete Optimization Method for Nuclear Fuel Management
Jean-Philippe Argaud
PDF
A-Modified Point Kernel Method to Estimate Reaction Rates in Reactors
S. Kitsos, L. Luneville
PDF
GASFLOW: The Theoretical Model to Analyze Accidents in Nuclear Containments, Confinements and Facility Buildings
J.R. Travis, T.L. Wilson
PDF
A Simulation of the Containment Activity Monitor
K.T. Tsang, C.R. Boss, G. Chartrand, M. Garceau, R.A. Gibb
PDF
Spatial Convergence of Flow Solutions Obtained With MODTURC_CLAS
x. Wu, J. Szymanski
PDF
Bruce NGS A/B Assessment of Reactor Vault Fans on Air Mixing Patterns
Kyle J. Um
PDF
Thermal Hydraulic Simulation of Moderator Heat Exchanger
S. Anil Lal, A. Rajakumar, G. Vaidyanathan, R. Srinivasan, S.C. Chetal
PDF
LINAC: An Acoustic Model for the CANDU-PHT System
F.B.P. Tran, A.P. Muzumdar
PDF
A Hydraulic Model of a Liquid Injection System with Gas Pockets
J.K. Szymanski
PDF
Numerical Solution of 3D Stokes Problems
R.Q.N. Zhou
PDF
Numerical Studies of Flow and Heat Transfer Around Fuel-Element Bearing Pads
A.O. Banas, M.B. Carver, C.A. Whitehead
PDF
Generalized Roe's Numerical Scheme for a Two-Fluid Model
I. Toumi, P. Raymond
PDF
Post-Test Simulation of the First CHAN 28-Element Experiment (Verification of CHAN-II MOD 6 Against Experiment)
M. Bayoumi, W.C. Muir, P.S. Kundurpi
PDF
Deposition-Dominated Cool ant Activity Analysis
P.J. Reid, F.C. Iglesias
PDF
Elastic-Plastic Stress Distributions Near the Endcap of a Fuel Element
M. Tayal, K.D. Hallgrimson, R.J. Sejnoha, P.N. Singh, R. DaSilva
PDF
The METEOR/TOUTATIS Code: A 2-D/3-D Code for Fuel Behaviour Simulation
B. Linet, X.Z. Suo
PDF
CANDU Bundle Junction: Misalignment Probability and Pressure Drop Correlation
E.K. Zariffeh, W.Y.K. Wong, S.N. Nanji
PDF
Research Reactor Simulation: A Study in Reactor Dynamics and Control
Jon K. Simonsen, Daniel S. Skinner, Kevan C. Crawford
PDF
Real-Time Simulation of the Korean Multipurpose Nuclear Research Reactor
M. Gauthier, M. Sabourin
PDF
Development and Testing of the Control Algorithm of the Korean Multipurpose Research Reactor
C. Papas, R. Henderson, D. McAllindon
PDF
Low Cost/Risk Approach for Verifying Modifications to Dynamic Plant Operation and Instrumentation & Control System Resulting from Steam Generator Replacement
Sadashiva S. Godbole, Gregory F. Malan
PDF
Reactor Parameter Simulation System
Kenny C. Gross, Kristin K. Hoyer
PDF
An Assessment of Prediction Methods of CHF in Tubes with A Large Experimental Data Bank
L.K.H. Leung, D.C. Groeneveld
PDF
Validation of the ASSERT Sub-Channel Code for Prediction of CHF in Standard and Non-Standard CANDU Bundle Geometries
J.C. Kiteley, M.B. Carver, R.Q-N. Zhou
PDF
A Generalized Critical Heat Flux Correlation for CANDU Fuel Geometries
N.N. Wahba, S.C. Tantirige, A.P. Muzumdar
PDF
An Investigation into the Accuracy of CHF Modelling in One-Dimensional Two-Phase Flow Analyses
Guy Hotte, T. Jouhanique
PDF
Prediction of Transient Post-Dryout Heat Transfer in Tubes
S.C. Sutradhar, J.C. Kiteley, M.B. Carver
PDF
Validation of ASSERT Subchannel Code for Maple-X10 Reactor Conditions
M.B. Carver, J.C. Kiteley, S.V. Junop, J.F. Wasilewicz
PDF