Canadian Nuclear Society
International Conference on Simulation Methods in Nuclear Engineering
Select Conference Type to see its Papers
OR
Use the search to search the whole database
| Conference | Year | Title | Author | Location |
|---|---|---|---|---|
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Some New Directions in System Transient Simulation | V.H. Ransom (INEL) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Development and Benchmarking of Integral Thermal-hydraulics Codes | R.E. Henry (FAI) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Thermal Hydraulics of LOFT Large Break Experiments and its Simulations with DRUFAN-02 | "A.B. Wahba, W. Pointner (Gesellschaft fur Reacktorsicherheit)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility | "J.P. Mallory, P.J. Ingham (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The GINNA Tube-Rupture Event: A Plant-Transient Benchmark for TRAC | "J.F. Lime, P.P. Jenks (LANL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Statistical Approach to Sensitivity Analysis of the Computer Simulation Codes | S.M. Aceil (American Technical Inst) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | RETACT Models in LINK's TMI-1 Advanced Simulator | "K.C Lea (The Singer Company), D.J. Boltz (GPU Nuclear)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Development of A Three-Dimensional Simulator of a DIDO-Type Reactor | "E. Nonbol (Riso National Laboratory, Denmark)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | EXPRIME: An Expert System to Analyse Primary Heat Transport System Accidents | "P. Tye (EPM), J.C. Amrouni (IR)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Scaling Laws for Simulating the CANDU Heat Transport System | "P.J. Ingham, V.S. Krishnan (AECL), P. Sergejewich (OH), K.H. Ardron (CEGB)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | PREMIERE: A Model to Calculate the Transfer of Deuterium Between the Moderator Fluid and the Cover Gas Volume in CANDU Reactors | "K.K. Fung, M. Garceau, W.I. Midvidy (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | A Nuclear Critically Simulator | "R.E. Anderson, W.L. Lesko, R.D. Sachs, H.C. Bachman (Rockwell International)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Kinetic Modeling for On-Line Advanced Plant Simulator | "J. Samuels, S. Kaya, S. Anghaie (Oregon State U)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Development of the Modal Kinetics Model for the Gentilly-2 G.S. | "J. Koclas (HQ), S. Alaoui (EPM), M.A. Petrilli (HQ)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | TRIVAC: A Modular Diffusion Code for Fuel Management and Design Applications | A. Hebert (EPM) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Semi-Analytical and Empirical Methods for Local Reactor Reactivity Estimation | "A.P. Muzumdar (OH), R.A. Bonalumi, D.G. Andrews (UT)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Producing Three-Dimensional Nodal Coupling Coefficients | "E.G. Derrick, G.V. Guardalben, A.L. Wight (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Fluid Flow Simulations in Complex Geometries | "P.F. Galpin, R.G. Huget, G.D. Raithby (UW)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Drift Flux Model in the ASSERT Sub-Channel Code | "M.B. Carver, R.A. Judd, J.C. Kiteley, A. Tahir (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Comparison of ASSERT-4 CHF Predictions with Measurements in 28-Element Simulated Fuel String | "J.K. Szymanski, G. Nurnberg, W.I. Midvidy (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Canonical Form of Turbomachine Characteristics (Four-Quadrants) and Other Three Port Devices | "R.J. Schneck (Schneck, Rosen Research Consultants)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Multilevel Transport Calculations | "R. Sanchez, J. Mondot (CEN, France)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Acceleration Strategies for the Interface Current Method | "G. Marleau, A. Hebert, R. Roy (EPM)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | RAVE - A View Factors Code for Arbitrary Geometry with Shadowing | "M.S. Milgram, S.L. Thompson (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Fuel Management Simulation for an Uprated CANDU-600 | D.A. Jenkins (AECL) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Optimization of Cobalt Adjusters with OPTEX-3 | "D. Rozon, M. Beaudet (EPM)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Poison Injection Model for a CANDU Reactor | "S.G. Lie, G.V. Guardalben, E.G. Derrick, H.G. Austman, A.L. Wight (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments | "G.H. Archinoff, J.C. Luxat, P.D. Lowe, K.E. Locke, A.P. Muzumdar (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Development of the MINI-START Code for Fuel Element/Pressure Tube Contact | "D.B. Reeves, G.H. Archinoff, K.E. Locke, A.P. Muzumdar (OH)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Validation of the Computer Code NUBALL for Simulation of Pressure Tube Asymmetric Ballooning Behaviour | P.S. Kundurpi (OH) | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | AMPTRACT: An Algebraic Model for Computing Pressure Tube Circumferential and Steam Temperature Transients Under Stratified Channel Coolant Conditions | "P. Gulshani, C.B. So (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | FAIG - A Code for Analysis of Irradiation-Induced Axial Dimensional Change in PWR Fuel Assemblies | A. Iisuka | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Use of Super-Computers in University Research | R.E. George | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Monte Carlo Neutron Transport on the CYBER-205 Supercomputer | "T.A. Tassou, E.M.A. Hussein, V.C. Bhavsar, V.G. Gujar" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Solution of the Few Group Neutron Diffusion Equations on Parallel Architecture Computers | "S.K. Zee, P.J. Turinsky" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Reactor-Physics Computer Codes to Microcomputers | "B. Rouben, K.S. Brunner, D.A. Jenkins (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | TOMCAT; A Transient and Operational Micro-Computer Based Analysis Tool | "K.S. Howe, P.R. Meyer" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Evaluation of Algorithms for the Solution of the Drift Flux Equations on Advanced Computers | E.D. Sills. J.M. Doster | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | "TRAC A Thermalhydraulics Code - Past, Present and Future" | R. Nelson | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Best Estimate Analysis of Prairie Island Plant Transients Using Dynode-P | "J.K. Kapitz, D.A. Rautmann, R.C. Kern" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | A Dynamic Model of A U-Tube Steam Generator for Real Time Simulation | B.W. Rhee | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Multi-Rate Integration Methods and Table Lookup Techniques Used in High Speed Dynamic Simulation of Nuclear Power Plants | "H.C. Yeh, W.E. Kastenberg, W.J. Karplus" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | The Rate Form of the Equation of State for Thermalhydraulic Systems: Numerical Considerations | "W.J. Garland, R. Sollychin (MacU)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | An Algorithm to Estimate Initial Discharge Rates for Stagnation Feeder Breaks | "C. Blahnik, S. Nijhawan" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Multifield Methods for Nuclear Thermalhydraulics Problems | S. Banerjee | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Validation of the TREAT Code Against Actual Plant Event Data | "D.F. Holderbaum, R.P. Ofstun" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Calculation of a Steam Generator Tube Rupture Accident Using THERMIT-UTSG | "S.T. Free, L. Schor" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Prediction of Steam Generator Depressurization Transients with the CATHENA Code | "B.N. Hanna, G.R. McGee, T.E. MacDonald (AECL)" | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | ATHENA Model for 4 x 350 MW(T) HTRG Plant Side-by-Side Steel Vessel Prismatic Core Concept | R.G. Ambrosek | Montreal |
| 2nd International Conference on Simulation Methods in Nuclear Engineering | 1986 | Capabilities of System Codes in Simulating Small Break LOCAS in PWRS | "F. D'Auria, G.M. Galassi, F. Oriolo" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | WIMS-AECL: A Review and Status Report | J. Griffiths (AECL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | MODTURC-CLAS: An Efficient Code for Analyses of Moderator Circulation in CANDU Reactors | "R.G. Huget, J.K. Szymanski (OH), P.F. Galpin (Advanced Scientific Computing), W.I. Midvidy (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Validation of the 2-D Heat Conduction Model in CATHENA | "D.J. Richards, W.G. Mathers, B.H. McDonald, S.R. Vatsya (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Implementation of a Control System Test Environment in UNIX | "C.R. Brittain (ORNL), L.A. Rovere (U of Tennessee), P.J. Otaduy (ORNL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | ABRAC: A Microcomputer-Based FORTRAN Code for Multi Cycle Burnup | A.P. Olson (ANL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Reactor Physics Modelling of the Maple Research Reactor | "P.A. Carlson, S.G. King (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Numerical Model for Counter-Current Flow | D.S. Rowe (Rowe & Assoc) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Analysis of Results of Natural Circulation Experiments in RD-14 Multiple Channel Test Facility | "P. Gulshani, J.N. Barkman (AECL), M.A. Wright, M.A. El-Hawary (NBP), H. Huynh (HQ)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | An Analysis of the Lateral Void Transfer Mechanisms in the ASSERT Subchannel Code | "P. Tye, A. Tapucu (EPM), S. Gencay (Istanbul Technical U)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Recent Extensions to the Capabilities of the Fuel and Wall Models in the ASSERT Subchannel Code | "A.O. Banas, M.B. Carver (AECL), D.S. Rowe (Rowe & Assoc)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of Two-Phase Flow Stability Behaviour of CANDU-Typical Heat Transport Systems | "J.P. Mallory, P.J. Ingham (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | "ASSERT 4 Simulation of the Distribution of Flow, Temperature and Critical Heat Flux in Horizontal Channels at High Pressure" | "J.C. Kitely, M.B. Carver (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Modelling of the Surroundings of MOX Fuel in PWRs | "G. Abu-Zaied, P. Grimm, J.M. Paratte (Paul Scherrer Inst, Switzerland)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | The Influence of Plutonium Distribution on the Space-Dependent Kinetics of CANDU | "D.H. Chung, A.R. Dastur (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of Protective Action by Shutdown-System1 Against Hypothetical Loss of Coolant From Various Initial Flux Configurations | "M.H. Younis, P. Soedijono, A.C. Mao, B. Rouben, M.A. Milley (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Treatment of Circular Boundary Conditions in Neutron Diffusion Calculations | "R. Roy, D. Rozon, A. Hebert (EPM), G. Hotte (HQ)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Application of On-Line Solution of 3 Dimensional Multigroup Finite-Difference Neutron Diffusion Equations in Reactor Power Control System | "P.S.W. Chan, M. Mamourian (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | CANDU 3 Reactivity Mechanism Deck Shielding Analysis | "A. Aydogdu, C.R. Boss (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of the Hydraulic Behaviour of Two Phase Flows in Blocked Subchannels | "A. Teyssedou, A. Tapucu, R. Camarero (EPM)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Level Swelling in Pressurizer and Steam Generators | W.S. Liu (OH) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Calculation of Countercurrent-Flow Flooding Limit Using CATHENA | B.N. Hanna (AECL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Application of Void Generation and Condensation Models to Predict Subcooled Boiling Data at Low Pressures | "V. Chatoorgoon, G.R. Dimmick, M.B. Carver, W.N. Selander (AECL), M. Shoukri (MacU)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Interaction of User and Models on System Code Predictions | "F. D'Auria, G.M. Galassi, P. Lombardi (UP)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Onset of Flow Stratification in Horizontal Rod Bundles | "S.I. Osamusali (UO), D.C. Groeneveld (AECL), S.C. Cheng (UO)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of the Plant Controller of LOVIISA Nuclear Power Plant | "K. Porkholm (IVO), M. Hanninen (Technical Research Centre of Finland)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Development of a Robust Model-Based Reactivity Control System | "L.A. Rovere (U of Tennessee), P.J. Otaduy, C.R. Brittain (ORNL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | TREAT Reactor Control Rod Scram System Simulations and Testing | "C.W. Solbrig, W.W. Stevens (ANL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | A Micro-Computer Containment Simulator to Support Training Programs for CANDU Reactor Operators | "J.A. Walsworth, E. Kennedy (ANSL), C.P. Guiry, R.A. Gibb, S.P. Turner (NBP)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | MICROSIM: A Real-Time Microcomputer-Based Simulator for Training Nuclear Power Plant Operators | "R. Moffett, R. Abdallah (AECL), M. Roberge (HQ)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Emergency Management System With Simulation and Training Facilities | "K. Sjoblom (IVO), B. Brehmer (U of Uppsala, Finland), S. Jakobsson (Technical Research Centre of Finland)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Use of Best Estimate Codes for Analysis of PWR Large Break LOCA | "K. Ardron, F.M. Evans, P.C. Hall (Central Electrical Generating Board, UK)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulations of Darlington Shutdown Cooling System | "I. Cheng (IR), R.Y. Chu, B. Phillips (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | "A Semi-Analytical, Inherently Parallel Method for LWR Thermal-Hydraulic Feedback" | "A.M. Ougouag, M. Vandermyde, B.G. Jones (U of Illinois)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Mathematical Modelling of Material Transport and Sludge Formation in Nuclear Steam Generators | "Y. Liner, M.B. Carver, A.O. Campagna (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Parity Simulation of a Pressurized Water Reactor System | "E.V. Depiante, J.E. Meyer (MIT)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Anti-Vibration Bar Model for the THIRST Computer Code | "A.O. Campagna, M.B. Carver (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Development of Square and Hexagonal Lattice Analysis Capability in WIMS-AECL | J.V. Donnelly (AECL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Generalization of the STAMM'LER Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries | "A. Hebert, G. Marleau (EPM)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Interface-Flux Nodal Transport Method | P. Kohut (Brookhaven National Laboratory) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Comparison of Monte Carlo and Interface Current Solutions to 3D Transport Problems | "G. Marleau, R. Roy, A. Hebert (EPM), E. Paradis (CAE)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Flow Regime Effects on the Neutronic Parameters of Liquid Metal-Gas Two-Phase Flow in a Fusion Reactor Coolant Channel | "J.C. Campeau, Jen-Shih Cheng (MacU)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Image Processing for Neutron Radiography | "H-W Syh (U of Nebraska), R.F. Saxe (North Carolina State U)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Thermalhydraulic Analysis of Containments | "M. Merilo (EPRI), T.L. George (Numerical Applications Inc)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Integrated Aerosol and Thermalhydraulics Modelling for CANDU Safety Analysis | B.H. McDonald (AECL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Application and Validation of the PHEONICS Code for Moderator System Conditions in a CANDU Nuclear Generating Station | "W.M. Collins (AECL), M. Garceau (HQ), M. El Hawary (NBP)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Water Droplet Aerosol Removal by Flashing Jet Impingement | H-W Chiang (AECL) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Thermal-Hydraulic Simulation of the Moderator System of Ontario Hydro's CANDU Reactors | "K.J. Riffert (Wardrop), K.K. Fung, W. Midvidy (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Easy Explicit Coupling Between Two Large Codes Using CRAY UNICOS | "G. Nicolas, E. Briere, F. Lux, S. Marguet (EdF)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of the Long Term-Cooling Behaviour After a PWR Loss of Coolant Accident Using RELAP5/MOD2 | "G. Willmott, M. El-Shanawany (NE)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Three-Dimensional Simulation of Jet Flow Impacting onto a Plate Inside an Enclosure | "A.K. Ahluwalia, A.M. Chan (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Prediction of Pressurizer Transients by the IDRIFF Two-Phase Simulation Code | "R. Sollychin, J.S. Chang, W.J. Garland (MacU)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Simulation of Feed/Bleed Operation in AGS Dew Point Monitoring | "J.M. Kenchington, A. Choi, D.G. Meranda (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Detailed Simulation of the Refuelling Operation for a Single Fuel Channel Using RFSP | "M.A. Milley (AECL), C. Newman (NBP)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Enhancements in FMDP Spatial-Control Algorithm and Xenon Time Search | "M.C. Beaudet (HQ), D.A. Jenkins (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | CANDU Reactor Regulating System Response Modelling in SMOKIN Code | "M.Z. Farooqui, M.B. Gold (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Improved Method for Calculation of Harmonic Modes for CANDU Reactors | "N. Roy, S.D. Arguner, A.U. Rehman, A.L. Wight (OH)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Optimization of Marine Pressurized Water Reactor In-Core Fuel Management | "S.K. Dewar, H.W. Bonin (CMRC/RMCC)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Preliminary Thermalhydraulics Analysis of the AMPS-1000 Reactor Using COBRA-IV and RELAP5/MOD2 | "A. Tahir, V. Tavasoli (ECSPS)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Application of FLOW3D to Flow Modelling in Small Pool Natural-Circulation and Forced-Circulation Reactors | "S.J. Marshall (UT), M.B. Carver (AECL), P.W. Shipp (MacU)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Dynamic Modelling of Primary Heat Transport System of KMRR for Real Time Plant Simulation | "B.W. Rhee, K.H. Lee, B.S. Sim, S.K. Oh (KAERI)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Three-Dimensional Calculations of Low-Flow Buoyant Jets in a MAPLE Flow Test Facility | "S.Y. Shim, D.K. Baxter (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Numerical Prediction of Transient Thermalhydraulic Behaviour of a MAPLE Finned Fuel Element Simulator | "P.J. Mills, S.Y. Shim (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Predicting the Distribution of Fuel Temperatures for a Single Channel Flow Blockage Scenario Using the Newly Developed Code CANSIM-PLE | "K.E. Locke, A.P. Muzumdar (OH), L.J. Watt, V.J. Langman (IR)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | FROMSFD: Transient Zircaloy Oxidation by Steam With Reduction of Urania | "L.D. McDonald, D.F. Simmons, F.C. Iglesias (AECL), D.B. Duncan (Heriot-Watt U, Scotland)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Two-Dimensional Finite-Element Analysis of Fin Efficiency for Finned Fuel Pin | "G.D. Harvel (MacU), S.Y. Shim, P.J. Mills (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Zircaloy Clad Failure Simulation in Rod Bundles Under LOCA Conditions | N.T. Saltos (Westinghouse Hanford) | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | ANSYS Thermal Analysis of Bearing Pad/Pressure Tube Interface | "A.P. Muzumdar, G.R. Berzins (OH), M. Krause, J.W. deVaal (AECL)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Sweep-Gas Experiment Interpretation and FREEDOM Code Validation | "L.D. McDonald, F.C. Iglesias (AECL), D.B. Duncan (Heriot-Watt U, Scotland), B.J. Lewis (CMRC/RMCC)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | "Influence of Graphite Discs, Chamfers, and Plenums on Temperature Distributions in High Burnup Fuel" | "A. Ranger, M. Tayal, P. Singh (AECL), I.A. El-Osery, K.A. Yasso (Nuclear Power Plants Authority, Egypt)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | Status of Natural Circulation Experiments in Multiple Channel RD-14M Test Facility | "P. Gulshani, J.N. Barkman (AECL), H. Huynh (HQ), M.A. Wright (NBP)" | Montreal |
| 3rd International Conference on Simulation Methods in Nuclear Engineering | 1990 | TREAT Reactor Control Rod Scram System Simulations and Testing | "C.W. Solbrig, W.W. Stevens (ANL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Dynamic Benchmarking of Simulation Codes | "R.E. Henry, C.Y. Paik, G.M. Hauser (FAI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Recent Trends in Methodologies for CANDU Finite-Core Analysis at AECL | B. Rouben (AECL) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Coupling Subroutine Version of ELOCA Code for High-Temperature Fuel Behaviour to CATHENA System Thermalhydraulics Code | "L.N. Carlucci, J.R. Gauld, V.I. Arimescu, D.J. Richards (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Overview of TUF Code for CANDU Reactors | "W.S. Liu, R.K. Leung, J.C. Luxat (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Uncertainty Analysis for Simulation Code Validation | "H.E. Sills, D. Evens, J. Pascoe (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Modelling Inlet or Outlet Feeder Voiding and Fuel Simulator Cooling Under Natural Circulation Conditions in the RD-14M Loop | "P. Gulshani (AECL), H.M. Huynh (HQ)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Assessment of CATHENA for Simulating Two-Phase Water Hammer | T.G. Beuthe (AECL) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Pre-and Post-Test CATHENA Simulations for RD-14M Critical Break Experiments | "E.J.M. Yetman, T.V. Sanderson (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Numerical Study of the Influence of the Void Drift Model on the Predictions of the ASSERT Subchannel Code | "P. Tye, A. Teyssedou, N. Troche (EPM), J. Kiteley (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Effect of the Position of an Orifice with Respect to an Elbow on Counter-Current Flooding | "S. Bedard, A. Teyssedou, P. Tye (EPM), W. Midvidy (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | An Investigation of the Local Non Uniformities in the Ignalina RBMK-1500 Reactor Core Characteristics | "B.R. Sehgal (Royal Institute of Technology), A. Balygin (Kurchatov Institute)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | "Distributed Fuel-Management Computation using RFSP, WIMS-AECL and PVM" | "P.J. Laughton, D.A. Jenkins (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Investigation of Error Sources during Core Reactivity Measurements | R. Blake (Utility Resource Associates Corp.) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Parallel Acceleration and Rebalancing Schemes for Solving Transport Problems Using PVM | "A. Qaddouri, R. Roy (EPM), B. Goulard (UdM)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Fuel Management Study of Refuelling of One-Quarter and One-Half of the Core at Point Lepreau | "M.A. Shad, H.C. Chow (AECL), C.W. Newman, R.W. Sancton (NBP)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | SCDAPSIM Reactor Systems Analyzer for Design and Beyond Design Basis Accident Conditions | "C.M. Allison, D.L. Hagrman, (INEL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Probabilistic Analysis of Maximum Channel Power Error - a Parametric Study | "A.P. Firla, P. Sermer (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Probabilistic Approach to Channel-Power-Limit and Bundle-Power-Limit Compliance Analysis | "F.A.R. Laratta, H.C. Chow (AECL), E.G. Young, C.W. Newman, R.E. Stone (NBP)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | CANDU 9 Moderator Temperature Predictions for Steady State and Accident Scenarios Using MODTURC-CLAS | "W.M. Collins (AECL), B. Wu (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Using Deterministic Methods for Research Reactor Studies | "E. Varin, S. Noceir, R. Roy, D. Rozon (EPM), C. Guertin (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Application of Uncertainty Analyses with the MAAP4 Code | "K. Nagashima (NUPEC), M. Alammar (GPU), H.C. Da Silva (TU), R.E. Henry (FAI), M. Kenton (D&M), D. Kuhtenia (TE), M. Kwee (OH), W. Ranval (EdF)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Development of the CAT Code-YGN 5&6 CVCS Analysis Tool | "S.W. Kim, S.H. Sohn, J.T. Seo, S.K. Lee (KAERI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Simulation of Relief Valve Dynamic Behaviour | "K.F. Hau, N.Y. Lee, A. Usmani (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Validation of FORTRAN Emulators for the G2 Varian Control Programs | G. Delorme (HQ) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | The Reactor Trainer: State-of-the-Art Classroom Learning | R.G. Stater (SURTCO Associates) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Simulation-Based Reactor Control Design Methodology for CANDU 9 | "M.K. Kattan, M.J. MacBeth (AECL), W.F. Chan, K.Y. Lam (Cassiopeia Technologies Incorporated)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Simulation of Reactor Power Cutback System Tests for YGN 3&4 | "J.T. Seo, S.W. Sohn, S.K. Lee (KAERI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Simple Model for Rewetting of Hot Tubes Limited by Flooding | "M. Shoukri, S.M. Nada (MacU), A.S. Huzayyin (Benha Higher Institute of Technology), A.F. El-Dib (Cairo U), A.A. Razzak (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Recent Advances in DSNP - A Simulation Language for Dynamic Simulation of Nuclear Power-Plant | "I. Silverman, M. Shapira, D. Saphier (Soreq-NRC)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Two-Fluid Effects on Reactor Thermal-Hydraulics | "W.S. Liu, R.K. Leung, J.C. Luxat (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | NUCIRC Simulations of a CANDU-Type Header Manifold Model | "G.D. Harvel, M. Soulard, R.F. Dam, P. White (AECL), G. Hotte (HQ), R. Moffet (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | SGTR Assessment Using MARS | "J.C. Raines, S.M. Dawson, B. Deitke, R.E. Henry (FAI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | STAR 3D Nodal Kinetics and Thermal/Hydraulic Model for the Pennsylvania State TRIGA Reactor | "M.A. Feltus, F.A. Alpan, M. DeChaine (Pennsylvania State U)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Validation of DRAGON Based on Lattice Experiments | G. Marleau (EPM) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Validation of WIMS-AECL Against Actual Operating History: Core Follow of Point Lepreau Nuclear Generating Station with POWDERPUFS-V and WIMS-AECL | "E.V. Carruthers, J.V. Donnelly (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Advances in Supercell Calculation Methods and Comparison with Measurements | "B. Arsenault (AECL), R. Baril, G. Hotte (HQ)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Storage of Natural-Uranium Fuel Bundles in Light Water: Reactivity Estimates | "K.T. Tsang, P.S.W. Chan, C.R. Boss (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Numerical Technique for Enchanted Efficiency and Stability for the Solution of the Nuclear Reactor Equation | "V.A. Khotylev, J.E. Hoogenboom (Delft U of Technology)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | The Importance of Proper Feedback Modeling in HWR | "D. Saphier, Z. Gorelik, M. Shapira (Soreq-NRC)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Gentilly-2 Overpower Transient Initiated by a Loss of Electrical Power | "A. Baudouin, C.H. Nguyen, G. Hotte (HQ), G.D. Harvel, M. Shad, M. Soulard (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Analysis of Uncertainties in Power Pulse Calculations Following a LOCA | "M.Z. Farooqui, A.H. Oslinger, M.B. Gold, R. Chu (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Prediction of Pressure Tube Ballooning Under Non-Uniform Circumferential Temperature Gradients and High Internal Pressure | "W.C. Muir, M.H. Bayoumi (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Water Level Instrumentation Simulation | "W.E. Berger, J.C. Raines, R.J. Hammersley, R.E. Henry (FAI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | PRESCON2 Predictions of Point Lepreau Containment Events | "M.S. Quraishi (Sadiq Yousuf Group, Inc.), R.A. Gibb (NBP), G. MacDonald (ANSL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Simulation of RD-14M Single-Phase Pump Rundown Tests Using the TUF Pump Model | "P.T. Wan, J. Pascoe, J. Anderson, C. Raczynski, R. Leung (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Validation of Radiation Heat Transfer in CATHENA | Q.M. Lei (AECL) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | TUF Validation Against LRV Test Data at Darlington NGS | "W.K. Liauw, B.S. Phillips, W.S. Liu, R.K. Leung (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | TUF Code Simulation of Darlington Nuclear Generation Two-Phase Pump Test | "S.I. Osamusali, T. Toong, R.Y. Chu (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Validation Exercise for the MAAP4 Containment Model | "C.Y. Paik, M.A. McCartney, R.E. Henry (FAI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | MACSIM: An Agent Oriented Simulation Code for the McMaster Nuclear Reactor | "P. Gerard, W.J. Garland, W.F.S. Poehlman (MacU)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Development of a Look-Up Table for Film-Boiling Heat Transfer Covering Wide Range of Flow Conditions | "L.K.H. Leung, N. Hammouda, D.C. Groeneveld (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Quenching of Metal Surfaces in a Narrow Annular Gap | "R.E. Henry, R.J. Hammersley (FAI)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Factors Affecting Fuel Bundle Motion Due to Reverse Flow | N.N. Wahba (OH) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Onset of Significant Void in 37-Element CANDU Fuel Bundles | "T. Balint, W.I. Midvidy (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | A Study of Coolant Thermal Mixing within CANDU Fuel Bundles using ASSERT-PV | "M.F. Lightstone, R. Rock (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Bulging of Pressure Tubes at Hot Spots Under LOCA Conditions | "C. Manu, A.C.D. Wright, R. Aboud, J.H.K. Lau, R.S.W. Shewfelt, D.B. Sanderson (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | First Experimental Results of the Thermal Behaviour of AECL's CANSTOR Spent Fuel Dry Storage Module | R. Moffett (AECL) | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | High Temperature Fuel Channel Simulations Using CATHENA | "G. Nurnberg, Q.M. Lei (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Modelling Thermalhydraulic/Thermal-Mechanical Behaviour of a Fuel Channel with Stratified Two-Phase Flow Using CATHENA | "Q.M. Lei, T.M. Goodman, D.B. Sanderson (AECL)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | Methodology for Fuel Channel Integrity in Large Break Loss of Coolant Accident | "M.H. Bayoumi, W.C. Muir (OH)" | Montreal |
| 5th International Conference on Simulation Methods in Nuclear Engineering | 1996 | FACTAR_SS Initial Fuel Conditions for Fuel Channel Transient Simulations | "H.E. Sills, Y. Liu (OH)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Refurbishment of Point Lepreau Generating Station | "P.D. Thompson (NBP), R. Jaitly, N. Ichiyen (AECL), M.A. Petrilli (MAPSAN)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Constitutive Model for Reinforced Concrete Applied in the Analysis of the Gentilly-2 Reactor Building | V. Gocevski (HQ) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | LWR Reactivity Accident Analysis and its Significance in the U.S. Regulatory Process | "D.J. Diamond, A.L. Aronson, B.P. Bromley (Brookhaven National Laboratory)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Approach and Methods to Evaluate the Uncertainty in System Thermalhydraulic Calculations | Francesco D∆Auria (UP) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Implementation of Low Void Reactivity Fuel in Bruce B | "R.M. Chun, F.C. Iglesias (BP), G.H. Archinoff (Candesco)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Generation IV Power for the Future: Status of the SCWR | R.B Duffey (AECL) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | 25-Years Three-Fluid Modeling-Experience: Successes and Limits | N.I. Kolev (Framatome) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | RELAP5/MOD3.2 Re-Analysis and Accuracy Quantification of LOFT Experiment L2-5 | "A. Petruzzi, W. Giannotti, F. D∆Auria (UP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A Restructuring of the CF/EDF packages for the MIDAS Computer Code | "S. H. Park, K. R. Kim, D. H. Kim (KAERI)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of a Transient Thermal-hydraulic Analysis Code for CARR | "W. Tian, J. Wang, Y. Guo, S. Qiu, D. Jia (Xi∆an Jiaotong University, China)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Validation of CATHENA MOD-3.5c/Rev 0 for Channel Coolant Voiding | "T.V. Sanderson, D.F. Wang (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | CATHENA New Post-Dryout Heat Transfer Methodology | "R.Girard (HQ), B.N. Hanna, L.K.H. Leung (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Bruce A Restart Phase B Commissioning Physics Tests - A Comparison between Measurements and Calculations | "C. Ngo-Trong, M. Gold, D. A. Jenkins, W. Shen, A. Mao, P. Schwanke (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Neutronic Simulations of the NRU Mk7 Fast-Neutron Rods for Material Testing | T.C. Leung (AECL) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Space-dependent Kinetics of CANDU-PHWR Based on Nodal Methods | "I.S. Hong, C.H. Kim (Seoul National University)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | SORO Post-Simulations of Bruce A Unit 4 In-Core Flux Detector Verification Tests | "E. Braverman, O. Nainer (BP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | RFSP Power Rundown Simulation of Bruce Power Unit 7 Shutdown System One (SDS1) Trip Test | "H. Albasha, O. Nainer" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Application of Nonlinear Iteration Semi-analytic Nodal Method in CANDU Reactor Fuel management | "H. Xiaodong, X. Zhongsheng (Xi∆an Jiaotong University, China)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | An Experimental Simulation Study of Debris Quenching in a Radially Stratified Porous Bed | "B.R. Sehgal, A.K. Nayak, A. Stepanyan (Royal Institute of Technology, Sweden)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Safety Analysis of RBMK-1500 Using Best Estimate Approach | "E. Uspuras, A. Kaliatka (Lithuanian Energy Institute)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of NSSS Transient Analyzer Based on Best-Estimate Codes for Pressurized Water Reactor | "H.-S. Lim, H.-G. Kim, Y.-K. Bae, S.-W. Lee, S.-J. OH, S.-J. Cho (KHNP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Safety Assessment of a Dry Storage Container Drop into Irradiated Fuel Bays | "Y. Parlatan, D. Oh, D. Arguner (OPG), Q.M. Lei, M.H. Bayoumi, T. Kulpa (NSS)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Simulation of Transient Heat Transfer in MACSTOR/KN-400 Module Storing Irradiated CANDU Fuel | "G. Sabourin (AECL), K.-H. Lee, J.-H. Yoon, B.-I. Choi, H.-Y. Lee, M.-J. Song (KHNP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Evaluation of Safety Margins During Dry Storage of CANDU Fuel in MACSTOR/KN-400 Module | "R. Beaudoin, R. Shill (AECL), K.-H. Lee; S.-H. Chung; J.-H. Yoon; B.-I. Choi; H.-Y. Lee; M.-J. Song (KHNP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Simulation of the Formation of Slugs in a Vertical-to-Horizontal Obstructed Flow | "N. Onder, A. Teyssedou (EPM), D. Roubtsov (McGill)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Single-Phase Pressure-Drop Model for Aligned and Misaligned CANDU Bundles | L.K.H. Leung (AECL) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Experimental Investigation of Inverted Annular Film Boiling for Vertical Up-Flow | "M.A. El Nakla, J. Yanga (UO), D.C. Groeneveld (AECL), S.C. Cheng (UO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Effect of Bearing Pad Height on Single-Phase Pressure Drop in Aligned and Misaligned 7-Element Bundle String | "M.K.Y. Ip, S.V. Irving, L.K.H. Leung (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Pressure Drop Tests For CANFLEX Bundles with High Bearing-Pads in Uncrept and 5% Uniformly Crept Channels | "S. K. Yang, L.K.H. Leung, Y. Guo (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Numerical Simulation of Turbulent Flow and Heat Transfer in Parallel Channel with an Obstacle and Verification of the Field Synergy Principle | "T. Wenxi, A. Myint, Q. Suizheng, J. Dounan (Xi∆an Jiaotong University, China)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | BOW: Comparisons of Creep Calculations with Analytical Solutions | "S.G. Xu (AECL), S.D. Yu (RU), M. Tayal, Z. Xu (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Analysis of Delayed Creep Rupture Test Conditions to Qualify New Calandria Tubes for CANDU-6 Reactors | "T. Nitheanandan, P.D. Neal (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Computer Simulation of Texture and Microstructure Transformation of Zr Alloys During the Annealing Process | "H. Li, J. Lin, J. Szpunar (McGill)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Computer Simulation of Hydrogen Ingress and Oxidation Kinetics on Zr-Nb Pressure Tubes | "H. Li, J. Lin, J. Szpunar (McGill)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Computer Simulation of Oxide Formation in Zr-Nb Pressure Tubes | "H. Li, J. Lin, J. Szpunar (McGill)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | The Crystal Structure of Pure and Doped Urania | "B. Szpunar (AECL), J. Szpunar (McGill)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Application of the Generalized Multigroup Method for a Continuous Gamma Spectrum Source | "I.K. Attieh, R.E. Pevey (University of Tennessee)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | 3D Large-scale Calculations Using the Method of Characteristics | "M. Dahmani, R. Roy, J. Koclas (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Application of a Combined Eulerian-Lagrangian Mesh Updating Method to the ZRod Cusping Problem | "D. Gilbert, W.J. Garland, W.F.S. Poehlman (MacU)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A First Attempt at a CANDU-6 Core Tracking Using Coupled DRAGON/DONJON Calculations | "E. Varin , G. Marleau (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Algebraic Collapsing Acceleration of the Characteristics Method with Anisotropic Scattering | "R. Le Tellier, A. Hebert, R. Roy (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A Novel Channel Selection Method for CANDU Refueling Based on BPANN and GA Technique | "H. Xiaodong, X. Zhongsheng (Xi∆an Jiaotong University)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | "MNRSIM: An Interactive Visual Model which Links Thermal Hydraulics, Neutron Production and Other Phenomena" | "D. Gilbert, W.J. Garland, T.Ha (MacU)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Adaptation of a Generic Model to Solve Flows and Pressures Hydraulic Networks for the Solution of Electrical Networks | "E.J. Roldfln-Villasana, Y. Mendoza-Alegr?a, (Instituto de Investigaciones El?ctricas, Mexico)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Assessment of Standard Formats for Data Exchange Between Scientific Codes | "R. Moffett (AECL), D. Shalaby (UW)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Optimization of Subchannel Simulations by Using Genetics Algorithms | "A. Nava-Dominguez, A. Teyssedou (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Optimization of Heat Exchanger Networks using Genetic Algorithms | "A. Teyssedou, J. Dipama (EPM), M. Sorin (CANMET Energy Technology Centre)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Sub-Channel Analysis by RELAP5 System Code of Boiloff Experiment (Test 5002) with NEPTUN Facility | "A. Petruzzi (UP), A. Bousbia Salah (Pennsylvania State University), F. D∆Auria (UP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Modelling of Pressure Tube Quench using PDETWO | "Y. Parlatan (OPG), Q.M. Lei (NSS), M. Kwee (BP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Use of CATHENA to Model Calandria-Tube/Moderator Heat Transfer after Pressure-Tube/Calandria-Tube Ballooning Contact | "H.Z. Fan, Z. Bilanovic, T. Nitheanandan (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Moderator Analysis of the Wolsong Units 2/3/4 for the Case of 35% RIH Breaks with a Loss of ECC Injection Using CFX-4.4 | "C. Yoon, B. W. Rhee, B-J Min (KAERI)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Assessment of ACR Moderator Circulation Design using CFD | "R. Bunama, L.N. Carlucci, G.M. Waddington (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | "Development, Qualification and Use of a Code With the Capability of Internal Assessment of Uncertainty" | "A. Petruzzi , W. Giannotti , F. D∆Auria (UP), K. Ivanov (Pennsylvania State University)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Analyses and Sensitivity Studies on VVER1000 Using the Best-Estimate Model RELAP5/PARCS | "J. Vedovi, K. Ivanov (Pennsylvania State University) , F.D∆Auria (UP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Best Estimate and Uncertainty Analysis of a Critical Large Break Loss of Coolant Accident at Darlington NGS | "N. Hunt (NSS), A. Muzumdar (OPG), H. Xie, P. de Buda, Y. Liu, E. Holliday (NSS), H. Sills (Auromont Research), R. Huget (R.G. Huget Research Inc)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Methodology for Calculating Doses to Equipments in Reactor Building Following LOCA/LOECI Accidents | "H. Huynh (HQ), R. Moffett (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of a Discharge Model for the Bopp & Reuther Degasser/Condenser Relief Valves for Heat Sink Assessment | "C. Hasnaoui (ECS Inc), H.M. Huynh (HQ)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Application of a CADIS-like Variance Reduction Technique to Electron Transport | "B. Dionne, A. Haghighat (University of Florida)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Simulation of Power Pulses During Large Break LOCAS in Natural and Slightly Enriched Cores in the Embalse NPP | "A. Parrondo, P. Serrano, M. Higa (Nucleoel?ctrica Argentina S.A.)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of a Micro-Depletion Model to Use WIMS Properties in History-Based Local-Parameter Calculations in RFSP | W. Shen (AECL) | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A Heterogeneous Coarse Mesh Transport Solution for a 2-D CANDU-6 Benchmark Problem | "B. Forget, G. Ilas, F. Rahnema (Georgia Institute of Technology, USofA)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Adjuster Rods Reactivity Evaluation Using a Detailed Geometry Model in DRAGON | "M. Beaudoin, J. Koclas, G. Marleau (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | VISWAM A Computer Code Package for Thermal Reactor Physics Computations | "V. Jagannathan, T.K. Thiyagarajan*, S. Ganesan, R.P. Jain, Usha Pal, and R. Karthikeyan (BARC)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Simulating Reactor Dynamics at the Nuclear Department DCEME | "A.C. Thompson (DCEME, HMS Sultan)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | ANSTO Replacement Research Reactor Training Simulator Development with FARSim | "A. Etchepareborda, C.A. Flury, F.Lema, F. Maciel, D.Alegrechi, G. Ibarra, M. Muguiro, M. D∆Amico. (Argentine National Atomic Energy Commission)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of Severe Accident Guidance Module for the SATS Simulator | "K.R.Kim, S.H. Park, D.H. Kim, Y.M. Song (KAERI)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A Framework for Evaluating Distributed Control Systems in Nuclear Power Plants | "C. O∆Donell, J. Jiang (UWO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Development of Support Platform for Research on Digitized Instrument and Control System in Nuclear Power Plant | "H. Rui, Y. Yanhua, L. Meng, Z. Ronghua (Jiao Tong University, Shanghai), X. Xiaozhen (Guangdong Nuclear Power Group, Shenzhen)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | The D2G2 Project: A New Software Tool for Nuclear Engineering Design in Canada | "P. Rh?aume, J.F. Lefebvre, R. Roy, J. Koclas (EPM)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | "Assessment of Critical-Heat-Flux Look-Up Tables, Experimental Data and Selected Correlations" | "A. Durmayaz (UO), D.C. Groeneveld (AECL), C. Cheng (UO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | An Improved Look-Up Table for Critical Heat Flux In Tubes | "D.C. Groeneveld, A.Z. Vasic (AECL), A. Durmayaz (Istanbul Technical University), J. Q. Shan (Xi∆an Jiaotong University, China), L.K.H. Leung (AECL),S.W. Peng (Huazhong University of Science and Technology, China), J. Yang, S.C. Cheng (UO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | An Investigation of the Effect of Axial Heat-Flux Distribution on Critical Heat Flux in Tubes | "J. Yang (UO), D.C. Groeneveld (AECL), S.C. Cheng (UO), L.K.H. Leung (AECL), M.A. El Nakla (UO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | An Assessment of Critical Channel Power Variations in Full-Core Implementation of CANFLEX Mk-IV Bundles with Natural Uranium Fuel | "Y. Guo, L.K.H. Leung (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Effects of Coherent Structures on Flow and Heat Transfer Characteristics in a Rod-Wall Gap Region | "D. Chang, S. Tavoularis (UO)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Investigations on Steam Explosion Phenomena with FARO and TROI Experiments | "A.K. Nayak, H.S. Park (Royal Institute of Technology, Sweden), A. Annunziato (Joint Research Centre, Ispra site), B.R. Sehgal (Royal Institute of Technology, Sweden)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Hydrogen Distribution and Mitigation in CANDU-6 Containment for LOCA/LOECC Accidents | "P. Hernu, R. Moffett (AECL), H. Huynh (HQ), T. Chapman (NBP)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Fission Product Distribution Simulation During Large LOCA Accidents for PHWR | "Y.M. Song, S.Y. Park, K.R. Kim, S.H. Park (KAERI)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | "The European Source-Term Evaluation Code ASTEC: Status And Applications, Including CANDU Plant Applications" | "J.P. Van Dorsselaere, P. Giordano, M.P. Kissane, T. Montanelli (IRSN), B. Schwinges (GRS), S.Ganju (BARC), L. Dickson (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | SOPHAEROS-IST 2.0 Validation: An Update on the Current Status | "L.W. Dickson, R.S. Dickson, R.J. Lemire, S. Sunder (AECL)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Neutron Beam and Shielding Design of MNR High-Speed Neutron Radiography Facility | "A.M. Khaial, G.D. Harvel, N. Harrison, J-S. Chang (MacU)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | TRANSITORI?N ˚ Program for the Simulation of Zone Liquid Level Evolution in Power and Reactivity Transients | "E. Coutsiers, M. Pomerantz, C. Moreno (Nucleoel?ctrica Argentina S.A.)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | The Residual Stress Evaluation For Expansion Process of Steam Generator Tubes | "C-S Kong, S-C Lee, D-N Shim (Doosan Heavy Industries & Construction, Korea)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Steam Generator Maintenance Virtual Simulation | "R. Lampron (Opti-Conseil inc, Canada)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | Simulation of CANDU 6 LLOCA Power Transients Terminated by SDS1 with a Full 2-Energy-Group Coupled RFSP-IST/CATHENA Approach | "R.D. McArthur, W.E. Ross (AECL), S. Kaveh (HQ)" | Montreal |
| 6th International Conference on Simulation Methods in Nuclear Engineering | 2004 | A Review of NUCIRC Development in Support of CANDU Plant Aging Assessments | "D.J. Wallace, W. Hartmann (AECL)" | Montreal |