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ConferenceYearTitleAuthorLocation
13th Nuclear Simulation Symposium1987"A New RFSP Model that Includes the Space Dependence of Fuel Temperature, Coolant Density and Power Density""D.A. Jenkins, B. Rouben (AECL)" Chalk River
13th Nuclear Simulation Symposium1987CONIFERS - A Reactor Core Analysis Program with Emphasis on Reactors with ChannelsR.S. Davis (AECL) Chalk River
13th Nuclear Simulation Symposium1987Lattice Characteristics that Influence the Change in Reactivity with Coolant Voiding in CANDU LatticesJ. Griffiths (AECL) Chalk River
13th Nuclear Simulation Symposium1987Choking Criterion for One-Dimensional Critical Multiphase Flow in Ducts and Open Channels"M. Dostie, Y. Mercadier (U de Sherbrooke)" Chalk River
13th Nuclear Simulation Symposium1987Assessing Spatial Effects in Aerosol Transport ModelsM. Razzaghi (AECL) Chalk River
13th Nuclear Simulation Symposium1987Analysis of Frictional Pressure Drop for High Pressure Steam-Water Stratified Flow in a Large Diameter Pipe"M.M. Wong, M. Kawaji (UT), K. Tasaka(JAERI)" Chalk River
13th Nuclear Simulation Symposium1987Investigation of Countercurrent Flooding Phenomena in Vertical-to-Inclined Elbows of Varying Angle"C.P. Tingle, M. Kawaji (UT)" Chalk River
13th Nuclear Simulation Symposium1987REGIME-3 Code for Prediction of Flow Regime Transition in a Two-Phase Manifold Flow"L. Lightstone, S.I. Osamusali, J.S. Chang (MacU)" Chalk River
13th Nuclear Simulation Symposium1987Numerical Modelling of Phase Distribution in Interconnected Subchannels"J.C. Kiteley, M.B. Carver, A. Tahir (AECL)" Chalk River
13th Nuclear Simulation Symposium1987Radionuclide Concentrations in the Steam-Condensate Supply System Due to Steam Generator Tube Chronic Leakage"W. Chan, R.Y. Chu, B. Phillips (OH)" Chalk River
13th Nuclear Simulation Symposium1987Darlington 'A' Real Time Simulation"P. Archer (AECL), E. Hung (OH)" Chalk River
13th Nuclear Simulation Symposium1987Real Time Simulation of the Pressurizer and Bleed Condenser for the Bruce NGS-B Training Simulator"M.D. Langan, A. Manz (OH)" Chalk River
13th Nuclear Simulation Symposium1987Running the CATHENA Thermohydraulics Code on a Supermicro Computer"K. Amrud, Q.S. Truong, R.L. Perch, V.Q. Tang (AECB), D.M. Kawa (Wardrop Engineering)" Chalk River
13th Nuclear Simulation Symposium1987PCTRAN/CND: Personal Computer Program for Predicting CANDU Reactor Thermalhydraulics"S.M. Sami, Y. Mercadier, M. Kraitem, A. Moreau (U de Sherbrooke), L.C. Po (Micro Simulation Technology)" Chalk River
13th Nuclear Simulation Symposium1987A Simple Steam Generator Model for Plant Optimization Studies"N.J. Spinks, M.R. Soulard (AECL)" Chalk River
13th Nuclear Simulation Symposium1987Characteristics of Two Phase Natural Circulation at Near Atmospheric Pressure in a Figure of Eight Loop"F.B.P. Tran (OH), W.J. Garland, J.S. Chang (MacU)" Chalk River
13th Nuclear Simulation Symposium1987A Simple Flow Stability Model for Figure-of-Eight Loop with Outlet Header InterconnectP. Gulshani (AECL) Chalk River
13th Nuclear Simulation Symposium1987Two-Phase Flow Stability Tests in RD-14"P.J. Ingham, G.R. McGee, J.P. Mallory, T.E. MacDonald (AECL)" Chalk River
13th Nuclear Simulation Symposium1987Small Inlet Header Break Experiments in RD-14"G.R. McGee, F.W. Barclay (AECL)" Chalk River
13th Nuclear Simulation Symposium1987Error Bounds on the Solutions of Parabolic Differential EquationsS.R. Vatsya (AECL) Chalk River
13th Nuclear Simulation Symposium1987The Allure of R-Functions"S.R. Douglas, M.S. Milgram (AECL)" Chalk River
13th Nuclear Simulation Symposium1987A Comparison of the Rate Form of the Equation of State to the Jacobian FormW.J. Garland (MacU) Chalk River
13th Nuclear Simulation Symposium1987"A Non-Linear, Finite Element, Heat Conduction Code to Calculate Temperatures in Solids of Arbitrary Geometry: The FEAT Program"M. Tayal (AECL) Chalk River
13th Nuclear Simulation Symposium1987Numerical Simulation of Phase Redistribution Caused by Obstructions and Bends"M.B. Carver (AECL), M. Salcudean (UBC)" Chalk River
13th Nuclear Simulation Symposium1987Simulating the Power Rundown Transient from Poison Injection System for a CANDU Reactor"N. Roy, M.Z. Farooqui, S.G. Lie, H.G. Austman, A.L. Wight (OH)" Chalk River
13th Nuclear Simulation Symposium1987Thorium-Fuelled CANDU Nuclear Reactor Optimal Fuel Management at Approach to Refuelling EquilibriumH.W. Bonin (RMC) Chalk River
13th Nuclear Simulation Symposium1987The Role of Enriched Fuel in CANDU Power Uprating"P.S.W. Chan, A.R. Dastur (AECL)" Chalk River
13th Nuclear Simulation Symposium1987Predicting Creep Response of CANDU Fuel Channel AssembliesR.G. Sauve (OH) Chalk River
13th Nuclear Simulation Symposium1987A Preprocessor for CDEPTH Input File Preparation"C.O. Poidevin, J. Tennant (OH)" Chalk River
13th Nuclear Simulation Symposium1987In-Reactor Deformation of Zr-2.5 wt% Nb Pressure Tubes"A.R. Causey, V. Fidleris, S.R. MacEwen (AECL), C.W. Schulte (OH)" Chalk River
13th Nuclear Simulation Symposium1987Irradiation-Induced Deformation of Zircaloy-2 Calandria Tubes in CANDU Reactors"A.R. Causey, V. Fidleris (AECL), R.A. Holt (OH)" Chalk River
13th Nuclear Simulation Symposium1987Modelling the Steam Temperature Distribution in CATHENA and Its Application to Pressure Tube Circumferential Temperature Distribution AnalysisC.B. So (AECL) Chalk River
13th Nuclear Simulation Symposium1987NUCCP (NUCIRC) Predictions of Channel Flow and Comparison with Site Measurements at the Point Lepreau Generating StationW.J. Hartmann (AECL) Chalk River
13th Nuclear Simulation Symposium1987The Phenomenology of the PHT Pump Trip Events"G. Delorme, (Groupe d'Analyse Nucleaire), L.J. Watt (IDEA Research)" Chalk River
13th Nuclear Simulation Symposium1987SOPHT Simulation of Valve Failures in the Heat Transport System of Bruce NGS-BD. Zobin (OH) Chalk River
13th Nuclear Simulation Symposium1987Simulation of ECCS Performance Using FIREBIRD III Mod. 1"V.Q. Tang, Q.S. Truong (AECB)" Chalk River
14th Nuclear Simulation Symposium1988Transdec: A Program to Calculate the Extra Decay Energy Generated in a Power Transient"C.R. Calabrese, C.R. Boss, B. Rouben (AECL)" Pinawa
14th Nuclear Simulation Symposium1988A Universal Driver for Collision Probability and Response Matrix Transport Codes"G. Marleau, A. Hebert (EPM)" Pinawa
14th Nuclear Simulation Symposium1988From Platinum to Mercury: The Alchemist's Nightmare"K.J. Serdula, G. Parent (Serdula Systems)" Pinawa
14th Nuclear Simulation Symposium1988Calculating Three-Dimensional Neutronic Transients on Microcomputers"B. Rouben, C.R. Calabrese (AECL)" Pinawa
14th Nuclear Simulation Symposium1988A Method for Simulating Grey Slabs in CANDU Reactors"A.R. Dastur, D.B. Buss (AECL)" Pinawa
14th Nuclear Simulation Symposium1988DERREP; A Computer Code for the Calculation of Decay Heat in CANDU Reactor Nuclear Fuel"R.P. Steadman, J.V. Marczak, M.K. O'Neill (OH)" Pinawa
14th Nuclear Simulation Symposium1988Simple Functions for the Fast Approximation of Light Water Thermodynamic Properties"W.J. Garland, B.J. Hand (MacU)" Pinawa
14th Nuclear Simulation Symposium1988Piecewise Polynomial Approximation of Thermodynamic Properties of Heavy Water"Y. Liner, B.N. Hanna, D.J. Richards (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Modelling of Nonhomogeneous Nonequilibrium Critical Two-Phase FlowS.M. Sami (U of Sherbrooke) Pinawa
14th Nuclear Simulation Symposium1988Numerical Predictions of Two-Phase Flow Parameters in Inverted U-tubes under Reflux Condensation"R. Girard, J.S. Chang (MacU)" Pinawa
14th Nuclear Simulation Symposium1988Investigation of CCFL in Pipe Elbows"L. Thomson, M. Kawaji, V.S. Krishnan (UT)" Pinawa
14th Nuclear Simulation Symposium1988Prediction of Pressurizer Transient by the IDRIFF Two-phase Simulation Code"R. Sollychin, J.S. Chang, W.J. Garland (MacU)" Pinawa
14th Nuclear Simulation Symposium1988The Dynamic Simulation of a Two-Node Non-Equilibrium 600MW CANDU Pressurizer System"H.O. Tezel, D.A. Meneley (UNB)" Pinawa
14th Nuclear Simulation Symposium1988MISSFINCH: Models for Steady Stratified Flow in CANDU HeadersP. Gulshani (AECL) Pinawa
14th Nuclear Simulation Symposium1988Steady-State Two-Phase Header Flow Model"H.G.O. De Man, Y. Feyginberg, W.I. Midvidy (OH)" Pinawa
14th Nuclear Simulation Symposium1988GENHTP - A New Heat Transfer Package for CATHENA"J.P. Mallory, P. Yuen, C.B. So (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Reactor Operator Companion for CANDU Heat Transport Systems"W.J. Garland, J.W.D. Anderson, J.D. Hoskins (MacU)" Pinawa
14th Nuclear Simulation Symposium1988CATHENA Study of Large LOCA Channel Behaviour"S.D. Grant, R.L. Dasilva (AECL)" Pinawa
14th Nuclear Simulation Symposium1988The Effect of Fuel Heat Transfer on Early Void Production Following a Large Pipe Break in CANDU Reactors"S.D. Grant, J.M. Hopwood (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Large Outlet Header Break Experiments in a CANDU-Type Heat Transport LoopP.J. Ingham (AECL) Pinawa
14th Nuclear Simulation Symposium1988Implementation of a Post-Dryout Model in the ASSERT Subchannel Code"A. Tahir, S. Robinovitch, P.R. Thibeault (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Thermalhydraulic Plant Modelling of a CANDU Reactor Including Plant Control Systems using CATHENA"F.W. Barclay, D.J. Richards (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Safety Aspects of Nuclear Battery Reactor DesignJ.V. Donnelly (AECL) Pinawa
14th Nuclear Simulation Symposium1988Some Aspects of MAPLE-10 Fuel Performance During Normal Operation"S. Girgis, I.E. Oldaker, G.E. Gillespie (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Recent Developments in Static Reactor Physics Modeling Techniques used for the Maple Research Reactor Program"P.A. Carlson, H.J. Smith, R.J. Ellis, A.G. Lee (AECL)" Pinawa
14th Nuclear Simulation Symposium1988"Comparisons of the Steady-State and Transient Thermal Behaviours of UO2, U-A1 and U3Si-A1 MAPLE Research Reactor Fuels""R.J. Ellis, P.A. Carlson, H.J. Smith (AECL)" Pinawa
14th Nuclear Simulation Symposium1988The Sensitivity of MAPLE-X10 Core Reactivity to Variations in the Three-Dimensional Coolant Void DistributionH.J. Smith (AECL) Pinawa
14th Nuclear Simulation Symposium1988Upper Bound Calculations of Aerosol Vapour Mass Concentrations in a CANDU Fuel Channel during Severe Fuel Damage AccidentsS.R. Mulpuru (AECL) Pinawa
14th Nuclear Simulation Symposium1988Pressure Challenges to CANDU Containment due to Hydrogen Combustion during AccidentsP. Klazek (OH) Pinawa
14th Nuclear Simulation Symposium1988A Solution Scheme for Aerosol Transport Models"S.R. Vatsya, M. Razzaghi (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Integrated Aerosol and Thermalhydraulic ModellingB.H. McDonald (AECL) Pinawa
14th Nuclear Simulation Symposium1988Effects of Antivibration Bars on the U-Bend Flow Distribution in Recirculating Steam Generators"L.N. Carlucci, J.M. Pietralik (AECL)" Pinawa
14th Nuclear Simulation Symposium1988"Techniques for the Estimation of Pressure Loss Coefficients of Bundle Junctions, Grid Spacers and Bearing Pads""S.C. Sutradhar, A. Tahir (AECL)" Pinawa
14th Nuclear Simulation Symposium1988Simulation of the SPEL Small Scale Moderator Experiments Using the General Purpose Fluid-Flow Heat Transfer Code PhoenicsW.M. Collins (AECL) Pinawa
14th Nuclear Simulation Symposium1988Thermalhydraulic Simulations for Plate-Type Nuclear Fuel Elements"H.E.C. Rummens, J.S. Chang, P. Ernst (MacU)" Pinawa
15th Nuclear Simulation Symposium1988Natural Circulation Experiments in the RD-14 Multiple Channel Thermohydraulics Loop"P.J. Ingham, J.P. Mallory (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Comparison of FIREBIRD III and CATHENA Code Simulations of a 100 Percent Reactor Outlet Header Break"J.N. Barkman, D.J. Richards, J.P. Mallory (AECL), M.A. Wright (NBEPC), H. Huynh (HQ)" Mississauga
15th Nuclear Simulation Symposium1988Small LOCA Analysis in Support of the Automatic PHTS Pump Trip Design for Point Lepreau NGS"M.A. Wright (NBEPC), D.J. Edgar (Systec)" Mississauga
15th Nuclear Simulation Symposium1988Analysis of Critical Inlet Header Break LOCA Experiments in the RD-14 Test Facility"N.K. Popov, G.R. McGee (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Enhanced Steam Pressure Control Routine for SOPHT-PA (Simulation of Primary Heat Transport - Pickering Nuclear Generating Station A"R.M. Sebastiano, N.A. Mitchell (OH)" Mississauga
15th Nuclear Simulation Symposium1988Modelling of the High-Speed Hydraulic Injection Transient Found in the CANDU Liquid (Poison) Injection Shutdown System"G. Schneider, H.G. Austman, W.I. Midvidy (OH)" Mississauga
15th Nuclear Simulation Symposium1988SPORTS-M Prediction of the Transition from Forced to Natural Circulation in a MAPLE Reactor"P.J. Mills, S.Y. Shim (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Reactivity Calculations for the RMC LEU Fuelled SLOWPOKE-2 Reactor"R.T. de Wit, H.W. Bonin (CRMC/RMCC), B.M. Townes (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Preliminary Thermohydraulics Analysis of the AMPS-1000 Reactor Core Using COBRA-1 VA. Tahir (ECSPS) Mississauga
15th Nuclear Simulation Symposium1988Application of FLOW3D to Flow Modelling in Small Pool Natural-Circulation and Forced-Circulation Reactors"S.J. Marshall, M.B. Carver, P.W. Shipp (AECL)" Mississauga
15th Nuclear Simulation Symposium1988The Analysis with Code TANK of a Postulated Reactivity-Insertion Transient in a 10-MW MAPLE Research ReactorR.J. Ellis (AECL) Mississauga
15th Nuclear Simulation Symposium1988An Empirical Correlation For D20 Two-Phase Critical Flow Prediction of the Henry-Fauske Model"M-R. Lin (AECL), M.A. Wright (NBEPC)" Mississauga
15th Nuclear Simulation Symposium1988Analysis of Countercurrent Flooding Data Obtained in Vertical-to-Inclined Pipes Containing Elbows of Varying Angle"M. Kawaji (UT), L.A. Thomson, V.S. Krishnan (AECL)" Mississauga
15th Nuclear Simulation Symposium1988"Applicability of the Homogeneous Equilibrium Model (HEM) In Horizontal Pipe, Annulus and Rod Bundle Flows""S.I. Osamusali, J.-S. Chang (MacU), D.C. Groeneveld (AECL), S.C. Cheng (UO)" Mississauga
15th Nuclear Simulation Symposium1988Improvement and Testing of a CANDU Pressurizer Dynamics Simulation"J.S. Pitre, D.A. Meneley (UNB)" Mississauga
15th Nuclear Simulation Symposium1988Real-Time Simulation of PHT Pump Low-Speed Drives for the Bruce NGS-B Training SimulatorF. Capogreco (OH) Mississauga
15th Nuclear Simulation Symposium1988Verification of the TUF Code Against the JUICE 1976 Standard Problems"A. Tomasone, W. Liu, J.C. Luxat (OH)" Mississauga
15th Nuclear Simulation Symposium1988Obtaining POWDERPUFS Ceil Cross Sections from WIMSM. Gold (OH) Mississauga
15th Nuclear Simulation Symposium1988Calculation of Device Static Reactivity Worth by Modal Analysis"M. Gold, M.Z. Farooqui, N. Roy (OH)" Mississauga
15th Nuclear Simulation Symposium1988Reactivity Transient Due to Malfunction of a Mechanical Zone Controller in the CANDU-3 ReactorV.K. Mohindra (AECL) Mississauga
15th Nuclear Simulation Symposium1988A Space-Time Reactor Simulation"G. Gaboury, W.J. Garland (MacU)" Mississauga
15th Nuclear Simulation Symposium1988"The Comparison of Calculated and Experimental Values of Fine-Structure Reaction Rates in CANDU-Type Lattices Containing (U233,Th)O2 Fuel""M.B. Zeiler, R.T. Jones, A. Celli (AECL)" Mississauga
15th Nuclear Simulation Symposium1988A Method for Calculation of Incremental Cross Sections for Rod-and-Tube Type Adjusters"S.D. Arguner, A.U. Rehman (OH)" Mississauga
15th Nuclear Simulation Symposium1988"A Fully Implicit, Back-Substituted Algorithm for Thermalhydraulic Networks""R.J. Wilson (EACS Inc), W.J. Garland (MacU)" Mississauga
15th Nuclear Simulation Symposium1988Real-Time Simulation of CANDU Heat-Transport System"J.D. Hoskins, W.J. Garland (MacU)" Mississauga
15th Nuclear Simulation Symposium1988An Iterative Method to Solve Large Sparse Lineal SystemsS.R. Vatsya (AECL) Mississauga
15th Nuclear Simulation Symposium1988Parity Simulation Applied to Reactor Physics Nodal Theory Transient AnalysisP.J. Laughton (AECL) Mississauga
15th Nuclear Simulation Symposium1988Calculating Array Criticality Using Thomas's Limiting Surface Density ModelJ.W. Thompson (AECL) Mississauga
15th Nuclear Simulation Symposium1988An Analytical Solution to the Equations for Long-Term Transport and Release of Fission ProductsK.R. Weaver (Shaftesbury Scientific Limited) Mississauga
15th Nuclear Simulation Symposium1988Recent Simulations of the Distribution of Flow and Temperature in Horizontal Bundles Using ASSERT-4"M.B. Carver, J.C. Kiteley, R.J. Morris (AECL)" Mississauga
15th Nuclear Simulation Symposium1988CATHENA Prediction of MAPLE-X10 Performance During a Complete Pipe Severance"T.E. MacDonald, S.Y. Shim (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Investigation of Refilling Behaviour of a Simulated CANDU Feeder Pipe"R. Thuraisingham, M. Kawaji (UT), J.C. Luxat (OH)" Mississauga
15th Nuclear Simulation Symposium1988MAPL3D Predictions of Three-Dimensional Flow Fields in a One-Fifth Scale Hydraulic Test Facility"D.K. Baxter, S.Y. Shim (AECL)" Mississauga
15th Nuclear Simulation Symposium1988A Model for Two-Phase Redistribution in Dividing Two-Phase Flow"J.D. Ballyk, M. Shoukri (MacU)" Mississauga
15th Nuclear Simulation Symposium1988Power Transient Following a Loss of Low Pressure Service Water Open System in Darlington NGS A"N. Roy, M.B. Gold, K.K. Fung (OH)" Mississauga
15th Nuclear Simulation Symposium1988The Effect of Loss of Regulation on the Severity of the Loss-of-Coolant Accident in the CANDU 6"M.H. Younis, S. Prawirosoehardjo, R. Calabrese, A.R. Dastur (AECL)" Mississauga
15th Nuclear Simulation Symposium1988RFSP Simulation of a Reactor-History Slice Featuring Saturated Zone-Control Compartments"M.A. Dencer, B. Rouben (AECL), E. Young (NBEPC)" Mississauga
15th Nuclear Simulation Symposium1988CANDU 600 Reactor Response to Localized Perturbations Such as Channel Fuelling"E. Young, R. Sancton, M. El-Hawary (NBEPC), R. Robinson (ANSL)" Mississauga
15th Nuclear Simulation Symposium1988Reactor Physics Simulation of Fast Reactivity Transients in the Nuclear BatteryJ.V. Donnelly (AECL) Mississauga
15th Nuclear Simulation Symposium1988SIMEX-77: A FORTRAN-77 Fuel Burnup History and Refuelling Simulation Program for Core Fuel Management at the Gentilly-2 Nuclear Generating Station"G. Hotte, M. Beaudet, J. Koclas, G. Pepin (HQ)" Mississauga
15th Nuclear Simulation Symposium1988Application of a Monte-Carlo Simulation Code for the Research and Development of Self-Powered Flux Detectors"T.C. Leung, R.J. Morris, S.J. Han (AECL)" Mississauga
15th Nuclear Simulation Symposium1988PRESCON2 Simulation of the OECD/CSNI Containment International Standard Problem #23"W.M. Collins (AECL), R.A. Gibb (NBEPC)" Mississauga
15th Nuclear Simulation Symposium1988Assessment of FFTF/MOTA and Thermal Reactor Irradiation Facilities for Advanced Tritium-Breeder-Material TestsR.E. Donders (AECL) Mississauga
15th Nuclear Simulation Symposium1988An Overview of Ontario Hydro's Nuclear Risk Assessment ProgramV.M. Raina (OH) Mississauga
15th Nuclear Simulation Symposium1988Real-Time Simulation of Electrical Distribution Systems"A. Abramovitch, N. Kratsios (CAE)" Mississauga
15th Nuclear Simulation Symposium1988CIRENE Fuel Bundle Integrity Following a Feeder Break"P.N. Singh, R. Sejnoha, M. Tayal (AECL), G. Valli (ENEA)" Mississauga
15th Nuclear Simulation Symposium1988Transient Thermal Analysis of an Idealized Fuel Element"G.R. McGee, J.W. DeVaal (AECL)" Mississauga
15th Nuclear Simulation Symposium1988An Improved Model for the Release of Fission Gas in CANDU Fuel"M. Tayal, A. Ranger (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Influence of Pellet. Shapes on Sheath Strains: ELESTRES Predictions vs Irradiation Measurements"N.C. Singhal, M. Tayal, T.J. Carter (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Heat Flux Distribution on a Finned Fuel Pin"J.E. Kowalski (AECL), I.C. Lim (KAERI), S.Y. Shim, P.J. Mills (AECL)" Mississauga
15th Nuclear Simulation Symposium1988Simulation of a Closed Two-Phase Thermosiphon with the CATHENA Code"B.N. Hanna, B.G. Taylor (AECL)" Mississauga
15th Nuclear Simulation Symposium1988A Method of Predicting CHF in Interconnected SubchannelsC.W. Snoek (AECL) Mississauga
15th Nuclear Simulation Symposium1988Two-Phase Pressure Drop Across Flow ObstructionsS.C. Sutradhar (AECL) Mississauga
16th Nuclear Simulation Symposium1991Inclined Feeder Refill Tests Conducted in the Cold Water Injection Test Facility - Analysis and ImplicationsP.T. Wan (OH) Saint John
16th Nuclear Simulation Symposium1991Validation of the CATHENA Code Using an RD-14M Thermosiphoning Test with Emergency Coolant Injection"J.P. Mallory (AECL), M.A. Wright (NBP), H. Huynh (HQ)" Saint John
16th Nuclear Simulation Symposium1991Critical Break Experiments in the RD-14M Thermalhydraulics Test Facility"A.J. Melnyk, P.J. Ingham, T.V. Murray" Saint John
16th Nuclear Simulation Symposium1991A Blind Simulation Study of an Out-of-Pile High-Temperature Fuel Channel Experiment"D.B. Sanderson, Q.M. Lei, J.P. Mallory (AECL), M. Bayoumi (OH)" Saint John
16th Nuclear Simulation Symposium1991Non-Linear Geometries of Continuous - Time Reactor DynamicsA.S. Adebiyi (OH) Saint John
16th Nuclear Simulation Symposium1991Power Feedback Effects in the SMOKIN CodeM. Gold (OH) Saint John
16th Nuclear Simulation Symposium1991NEACRP Standard Problem Exercise on Criticality Codes for Dissolving Fissile Oxides in Acids - A Reference Method for Treating the Fuel Double Heterogeneity"A. Santamarina, H.J. Smith (CEA), G.E. Whitesides (ORNL)" Saint John
16th Nuclear Simulation Symposium1991Comparison of Burnup Histories Calculated Using the Diffusion Theory and Flux Mapping Approaches"G. Hotte, M. Beaudet, A. Baudouin (HQ), A.C. Mao, D.A. Jenkins (AECL)" Saint John
16th Nuclear Simulation Symposium1991Experimental Verification of Regime-4 Code for Prediction of Flow-Pattern Transitions in a Horizontal 37-Rod Bundle Flow"S.I. Osamusali (OH), J.S. Chang (MacU)" Saint John
16th Nuclear Simulation Symposium1991ASSERT-IV Thermalhydraulics Subchannel Analysis Code Simulation of Dryout Power and Pressure Drop in a Horizontal 37-Rod Bundle Fuel Channel Including the Effect of Pressure Tube Creep"J.C. Kitely, M.B. Carver, Y. Liner, B.P. Bromley, I.K. McCracken (AECL)" Saint John
16th Nuclear Simulation Symposium1991SOPHT-RFI: A Thermalhydraulic and Dynamic Model for Reverse Flow Impact Scenario"F.B.P. Tran, K. Locke, A.P. Muzumdar (OH)" Saint John
16th Nuclear Simulation Symposium1991Experimental Study of Convective Mass Transfer Rates Using an Evaporative Mass Transfer Technique in Obstructed ChannelsT.S. Balint (OH) Saint John
16th Nuclear Simulation Symposium1991Some Aspects of the Criticality Safety Analysis of a Fissile Solution Storage TankJ.W. Thompson (ANSL) Saint John
16th Nuclear Simulation Symposium1991Reactivity Feedback Effects in the MAPLE-X10 Reactor Modelled As Changes in Two-Group Cross Sections in the Code TANK"R.J. Ellis, K.A. Litwin (AECL)" Saint John
16th Nuclear Simulation Symposium1991Optimization of a New Flux-Mapping Detector Layout for the CANDU 6 Reactor"K. Ossia, C.M. Bailey (AECL)" Saint John
16th Nuclear Simulation Symposium1991Accuracy of the Improved Quasistatic Method as Applied to CANDU Transient Analysis"P.S.W. Chan, A. Dastur (AECL)" Saint John
16th Nuclear Simulation Symposium1991Simulation Studies of On-Line Reactivity Digital Control Using Inverse Kinetics"W.M. Ratemi (Alfateh U, Tripoli), W.M. El-Ghadamsi, A.K. Belaid (Tajura Research Center, Tripoli)" Saint John
16th Nuclear Simulation Symposium1991Modelling of Two-Phase Natural Circulation in the MAPLE-MNR Primary Cooling Loop"G.D. Harvel, V.S. Krishnan, J.S. Chang (MacU), J.E. Kowalski (AECL)" Saint John
16th Nuclear Simulation Symposium1991Recent Model Developments in NUCIRC and Application to CANDU 6 Heat Transport System Performance Evaluation"M.R. Soulard, K.F. Hau (AECL)" Saint John
16th Nuclear Simulation Symposium1991Parallel Processing and the Simulation of the CANDU Reactor: Study of the NUCIRC Code on a MIMD Architecture"J.M. Lina, C.K. Scott (ANSL), B. Goulard, M. Mayrand (UdM)" Saint John
16th Nuclear Simulation Symposium1991Comparison of CATHENA and CHAN2A (Mod 1) Code Predictions For LOCA/LOECC Conditions"N.C. Singhal, A.C.D. Wright, V.I. Nath (AECL)" Saint John
16th Nuclear Simulation Symposium1991Commissioning of the Point Lepreau GS CANDU 600 Training Simulator"D.B. Reeves (Reeves Technology), D.L. Stafford, N.C.M. MacLean (NBP)" Saint John
16th Nuclear Simulation Symposium1991Real Time Simulation of the Point Lepreau Boiler"J. Salim, G. Salim (CAE)" Saint John
16th Nuclear Simulation Symposium1991Mass Conservative Hydraulic Network SolverJ. Pitre (UNB) Saint John
16th Nuclear Simulation Symposium1991A Graphic Interface for DSNP"H.G. Noye, J. Pitre (UNB)" Saint John
16th Nuclear Simulation Symposium1991The Secondary Side of DSNP"N. Arbeau, D.A. Meneley (UNB)" Saint John
16th Nuclear Simulation Symposium1991Display of RD-14M Data With IsoVu"J.B Hedley, R.S. Swartz (AECL)" Saint John
16th Nuclear Simulation Symposium1991Pre and Post-Processing CATHENA Simulations"S.D. Grant, P.H. Ta (AECL)" Saint John
16th Nuclear Simulation Symposium1991A Simulation Model for One-Dimensional Two Phase Flow"J. Zhang, D.A. Meneley (UNB)" Saint John
16th Nuclear Simulation Symposium1991Radiative Heat Transfer in a Partially-filled CANDU Reactor Channel"T. Taryo, E. Hussein (UNB)" Saint John
16th Nuclear Simulation Symposium1991The Development of the T-Bearing Pad and of Thin-Wall Fuel"S.J. Barnes, R. Sejnoha (AECL), E. Kohn (OH)" Saint John
16th Nuclear Simulation Symposium1991Modelling Fission Product Releases Due to UO2 Oxidation In A Steam Environment"R. Aboud, V.I. Nath (AECL), R. Hu (HQ)" Saint John
16th Nuclear Simulation Symposium1991Analysis of Temperature Distribution In A Proposed Fuel Element Bowing Simulator Using The FEAT Code"B. Wong, M. Tayal (AECL), E. Kohn (OH)" Saint John
16th Nuclear Simulation Symposium1991Simulation of CANDU 6 LISS Tests"R.D. McArthur, B. Rouben (AECL), R. Robinson, L. Boruvka (ANSL), P.D. Thompson (NBP), A. Baudouin, J. Koclas (HQ)" Saint John
16th Nuclear Simulation Symposium1991Transition In and Out of Two Pump Operation in a CANDU 600"R. Girard, P.D. Thompson, D.F. Weeks (NBP)" Saint John
16th Nuclear Simulation Symposium1991Post-Dryout Behaviour During Flow Oscillations"N.N. Wahba, A.P. Muzumdar (OH)" Saint John
16th Nuclear Simulation Symposium1991Automatic Pump Trip Design Under Accident Scenarios for Gentilly 2 NGS"H.M. Huynh, C.H. Nguyen (HQ), J-C. Amrouni (Enaq du Quebec)" Saint John
16th Nuclear Simulation Symposium1991Fuelling Machine Off-Reactor LOCA Analysis for a 600 MW CANDU Reactor"R.A. Gibb (NBP), R.H. Hu (HQ), H.E. Sills, Y.X. Liu (IDEA Research)" Saint John
16th Nuclear Simulation Symposium1991Comparison of CATHENA MOD-3.3h and FIREBIRD-III Mod1 Code Predictions for a Feeder Break in the CANDU 600 Reactor"T.K. Min, D.N. Mori, J.N. Barkman (AECL), P.D. Thompson, M.A. Wright (NBP), H. Huynh (HQ)" Saint John
16th Nuclear Simulation Symposium1991Passive Design Options for CANDU"N.J. Spinks, J.T. Dunn, T.C. De Mello, S. Azeez (AECL)" Saint John
16th Nuclear Simulation Symposium1991Experimental and Analytical Studies of Water Hammer in a Piping Network"A. Lai, K.F. Hau, M.L. Goel, C.W. So (AECL)" Saint John
16th Nuclear Simulation Symposium19913-D Simulation of Moderator Circulation For A Large Loss of Coolant Event"V. Yee, W.M. Collins (AECL)" Saint John
16th Nuclear Simulation Symposium1991Using ELESTRESS and NUCIRC to Determine CCP Penalties Associated with Heavy Bundles"A. Chan, B. Wong, A.M. Manzer (AECL)" Saint John
16th Nuclear Simulation Symposium1991An Analysis of CATHENA/PACE Predictions of Aerosol Transport In A Simulated Primary Circuit"D.J. Wallace, B.H. McDonald (AECL)" Saint John
16th Nuclear Simulation Symposium1991Numerical Simulation of the Initiation of Detonation Due to Shock Focusing"D.D. Radford, C.K. Chan, D.P. McCooeye (AECL), R.S. Azad (UM)" Saint John
16th Nuclear Simulation Symposium1991CREM - A New Thermalhydraulic Code for Containment Impairment Analysis"J.O. Oyinloye, M.J. Lewis (Electrowatt), C.K. Scott (ANSL)" Saint John
16th Nuclear Simulation Symposium1991Process Fault Verification System"P. Piumsomboon, D.A. Meneley, R. Girard (UNB)" Saint John
16th Nuclear Simulation Symposium1991Process Noise Based Monitoring and Diagnostics in Nuclear Power PlantsO. Glocker (UNB) Saint John
16th Nuclear Simulation Symposium1991Applying Multivariate Autoregressive Modelling and Sequential Probability Ratio Test to Nuclear Power Plant DataO. Glocker (UNB) Saint John
16th Nuclear Simulation Symposium1991Bulk Power Limits for the CANDU-6 Reactor"J. Handbury (ANSL), C.W. Newman, E.G. Young (NBP)" Saint John
18th Nuclear Simulation Symposium1994The Use of Shell Scripts as Analysis Tools"G.D. Gaboury (OH), H.J. Smith (Leathern-Smith Consulting)" Pembroke
18th Nuclear Simulation Symposium1994Beyond DragonAlain Hebert (EPM) Pembroke
18th Nuclear Simulation Symposium1994The Derivation of Burnup-Chain and Pseudo-Fission-Product Nuclear Data for a WIMS-AECL ENDF/B-VI-Based Cross-Section Library"P.J. Laughton, I.C. Gauld (AECL)" Pembroke
18th Nuclear Simulation Symposium1994Towards the Generation of a Consistent Reactor Cross-Section Database for CANDU-6 Using DRAGON"E. Varin, G. Marleau, R. Roy (EPM)" Pembroke
18th Nuclear Simulation Symposium1994A Simplified Heterogeneous Bl Model with Isotropically-Reflected Neutrons on Assembly Boundary"I. Petrovic, P. Benoist, G. Marleau (EPM)" Pembroke
18th Nuclear Simulation Symposium1994Estimates of Void Reactivity Coefficients with MCNP and WIMS-AECLM.S. Milgram (AECL) Pembroke
18th Nuclear Simulation Symposium1994On the Calculation of Void Effect in CANDU Using a Lattice Cell CodeJ. Whitlock (MacU) Pembroke
18th Nuclear Simulation Symposium1994Parametric Analysis of the DUPIC Fuel Cycle"H. Choi, B. Rhee, H. Park (KAERI)" Pembroke
18th Nuclear Simulation Symposium1994Experiments in ZED-2 to Study the Physics of Low-Void Reactivity Fuel in CANDU"M.B. Zeller, A. Celli, G.P. McPhee (AECL)" Pembroke
18th Nuclear Simulation Symposium1994Analysis of Substitution Experiments in ZED-2 with Physically Realistic Model AdjustmentsR.S. Davis (AECL) Pembroke
18th Nuclear Simulation Symposium1994Simulation of the 1992 SDSl Trip Test at Point Lepreau"D.A. Jenkins (AECL), E.G. Young (NBP)" Pembroke
18th Nuclear Simulation Symposium1994Simulation of Reactivity Control Devices in a CANDU-6 Reactor Using DRAGON"G. Marleau, R. Roy (EPM), B. Arsenault (AECB)" Pembroke
18th Nuclear Simulation Symposium1994Predictions of Bubbly Flows in Vertical Pipes Using Two-Fluid Models in CFDS-FLOW3D Code"A.O. Banas, M.B. Carver, D. Unrau (AECL)" Pembroke
18th Nuclear Simulation Symposium1994Analysis of Passive Heat Transport for an Advanced CANDU Containment"M. Krause, S. Jones, P.M. Mathew (AECL)" Pembroke
18th Nuclear Simulation Symposium1994ASSERT Development and Validation: Recent Progress"J.C. Kiteley, M.B. Carver, G.M. Waddington, R.Q.N. Zhou, Y. Liner (AECL)" Pembroke
18th Nuclear Simulation Symposium1994ASSERT/NUCIRC Commissioning for CANDU 6 Fuel Channel CCP Analysis"R.F. Dam, J.C. Kiteley, M.R. Soulard, M.B. Carver, K.F. Hau (AECL), G. Hotte (HQ), P.D. Thompson (NBP)" Pembroke
18th Nuclear Simulation Symposium1994Application of a Neural Network in the Prediction of Critical Heat Flux"K.J. Kamerman, R. Sollychin, S. Doerffer, E. Zariffeh, J. Scott, V. Lyengar (AECL)" Pembroke
18th Nuclear Simulation Symposium1994The Effect of Flow Transients on CHF at CANDU-Reactor ConditionsS.C. Sutradhar (AECL) Pembroke
18th Nuclear Simulation Symposium1994Sensitivity of the Primary Heat Transport System Behaviour to Different ECC Assumptions and to Different Pump Trip Delays Used During a Small Break SimulationA.V. Galia (NBP) Pembroke
18th Nuclear Simulation Symposium1994Large Break Loss-of-Coolant Accidents Analysis Using the TUF Code"R.Y. Chu, W.W. Yousef, W.C. Chan (OH)" Pembroke
18th Nuclear Simulation Symposium1994Best Effort Analysis of Critical Large Loss-of-Coolant Accident in Darlington NGS"W.W. Yousef, A. Tahir, J. Pascoe, J.C. Luxat (OH)" Pembroke
18th Nuclear Simulation Symposium1994CANDU 6 and RD-14/RD-14M ThermosyphoningM.R. Lin (AECL) Pembroke
18th Nuclear Simulation Symposium1994Computer Simulation of Initiation of Detonation by Shock Focusing"C.K. Chan, F. Torchia, A.M. Guerrero, J. Loesel Sitar (AECL)" Pembroke
18th Nuclear Simulation Symposium1994The Role of Simulation in CANDU 3 Fuel Handling Control System Design"N.H. Brown, D. Arapakota (AECL)" Pembroke
18th Nuclear Simulation Symposium1994Simulation of the Transport of Fission Products in the Fuel-to-Sheath Gap of Defective CANDU Fuel Rods"H.W. Bonin, B.J. Lewis (CMRC/RMCC)" Pembroke
18th Nuclear Simulation Symposium1994Simulation of 18O and 3H Distributions in the Atikokan Research Area"D.U. Ophori, T. Chan (AECL)" Pembroke
18th Nuclear Simulation Symposium1994Sensitivity Analysis of Crack Leakage Predictions of LEAK-RATE Version 1.0 Code"S.I. Osamusali, R.Y. Chu, W.C. Chan (OH)" Pembroke
18th Nuclear Simulation Symposium1994Analysis of Bearing-Pad to Pressure-Tube Contact Heat Transfer"T. Nitheanandan, Q.M. Lei, R.G. Moyer (AECL)" Pembroke
20th Nuclear Simulation Symposium1997The Method of Subgroups in the Calculation of Shielded Cross-Sections for WIMS-AECL"H. Chen, P. J. Laughton (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997On the Preparation of Library Data for an Implementation of the Method of Subgroups in WIMS-AECLP.J. Laughton (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Calculation of the Volumetric Heat Generation Rate Radial Profile in a Cylindrical Fuel Rod"V.I. Arimescu, M. Couture, M. Klein, A. Williams (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997An Acceleration Scheme for the Multigroup Sn Equations with Fission and Thermal Upscatter"B.T. Adams (Delft U of Technology, The Netherlands), J.E. Morel (UCLA)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997History-Based Calculations Using WIMS-AECL in RFSP"B. Arsenault, J.V. Donnelly, D.A. Jenkins (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997CATHENA Study of Two phase Water Hammer Inter-Peak TimingT.G. Beuthe (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Preliminary Investigation of the Solution of Sparse Matrices in CATHENA"T.G. Beuthe, J.B. Hedley (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Refill Effectiveness using High-Boiling Point Emergency CoolantG.R. McGee (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Darlington NGS A SGECS Condensation Induced Waterhammer Analysis using the TUF Code"C.W. So (AECL), P.L. Chang, D.G. Merandan (OH)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997A Three-Dimensional Modeling Analysis of CANDU 9 End-Shield Cooling Effects with CFX-4: A Preliminary Report"Y. Zhuang, A.O. Banas, R.Q.N. Zhou (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Analysis of the Fast Neutron Spectrum Inside the Materials Test Bundles in the NRU LoopsT.C. Leung (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Estimates of the Neutron Flux Distribution in an End-Fitting of the Bruce Unit 2 using Analog Monte-CarloM.S. Milgram (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Study of Nuclide Field Behaviour in Reactor with Continuously Changing Core Parameters"V.A. Khotylev, J.E. Hoogenboom (Delft U of Technology, The Netherlands), D.R. Kingdon, A.A. Harms (MacU)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Validation and Benchmarking of the HELIOS/RAMONA Model of Dodewaard"B.T. Adams (Delft U of Technology, The Netherlands), L. Moberg, R. Stamm'ler, A. Ferri, F. Guist (Scandpower, Norway)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997The Placement of Lateral Region in ID MTR Fuel Lattice Cell Models"S. Day, W.J. Garland (MacU)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Photoneutron Source Strength Studies in Pickering Reactors"M.W. Hersey, K.F. So, C.G. Olive, F.C. Shanes (OH)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997An Analysis of the Effect of Correlation of Response in the System Reliability Analysis in Seismic PSA of Nuclear Power Plants"Y. Watanabe, T. Oikawa, M. Kondo, M. Mizuno, K. Muramatsu (JAERI)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Development of a Computational Framework of Uncertainty Analysis for Level 2 PSA to Consider both Aleatory and Epistemic Uncertainties"K. Muramatsu, M. Himi (JAERI), K. Amagasa (Toshiba)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Optimisation of Operating Envelope and Safety Margin Using PRA Methods"C. Stoica (Cernavoda), C.K. Scott (ANSL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997A Spatial Convergence Study for Flows and Hydrogen Distribution in the CANDU 6 Reactor Vault following a Loss of Coolant Accident using the Gothic Containment Analysis Code"T.H. Nguyen, W.M. Collins (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Assessment of Refuelling Effect in High Power Channel on Fission Product Releases for Following an End-Fitting Failure"K.M. Lee (KNFC), K.M. Nho (KEPRI)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Numerical Schemes in CANSIM and Some Sensitivity StudiesV.I. Arimescu (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Fission Product Inventory and Distribution at Point Lepreau Generating Station"R.A. Gibb (NBP), P.J. Reid, T.J. Chapman (ALARA Research)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997NUCIRC Simulation of a Large Header for the CANDU Type Nuclear Reactor Heat Transport System"A. Kwan (MacU), R. Dam, M. Soulard, G.D. Harvel, V.S. Krishnan. (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Detailed Simulation of Ultrasonic Inspections"K.R. Chaplin, S.R. Douglas, D. Dunford, L.F.P. Lo, C.A. Daza (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Modelling Techniques for Vanadium Detector Compensation"J.C. Handbury (ANSL), C.W. Newman (NBP)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Dynamic Modelling for Shutdown-System-1 Depth AnalysisD.A. Jenkins (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Reactor Physics Simulation of the MNR January 1994 Fuelling IncidentH. Basha (MacU) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Effect of Pressure Tube Creep on the Void Coefficient of a CANDU Fuel BundleM.S. Milgram (AECL) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997System for Neutronic and Thermalhydraulic Diagnostics of Channel Type Reactor Parameters"V.A. Khotylev (Delft U of Technology, The Netherlands), N.V. Schukin, A.V. Filatov, S.D. Romanin, A.A. Semenov (Moscow Engineering Physics Institute), Y.B. Chizhevskiy (Kursk NPP), V.S. Sidorov (Kurchatov Institute, Russia)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997A Scaling Law Verification of the Delft Simulated Reactor (DESIRE)"B.T. Adams (Delft U of Technology, The Netherlands)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Development of a Model for Calculating Sheath Thermocouple Finning Losses for Application in In-Reactor Severe Fuel Damage Tests"L.C. Walters, J.W. DeVaal, N.K. Popov (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Transient Melting and Re-Solidification Model of CANDU Core Debris in Severe Accidents"J.T. Rogers, M,. Lamari (CU)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997CATHENA Model of the CANDU 9 End Shield Cooling System in the Event of Loss of Forced Circulation"N. Popov, L.A. Morris, D.N. Padhi (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Thermalhydraulics Response of a Conceptual CANDU Reactor with a Highly Advanced Core Subject to Various Loss-of-Coolant Accidents"J. Vechiarelli, R.F. Dam, K.F. Hau, F.J. Doria (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Safety Analysis Uncertainty Related to Design and Manufacturing Quality AssuranceE.N. Sokolov (Siberian Directorate of Gosatomnadzor of Russia) Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997A Generalized Prediction Method for Single-Phase Pressure Drop in a String of Aligned CANDU-type Bundles"L.K.H. Leung, D.C. Groenveld, (AECL), G. Hotte (HQ)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Critical Heat Flux Evaluation of a Conceptual Fuel Bundle Design with the ASSERT Subchannel Code"R.F. Dam, K.F. Hau, J. Vecchiarelli, N. Lee (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Simulation of CANDU Bundle Cross-Sectional Averaged Actual Flow Quality and Void in One-Dimensional Two-Phase Flow Models"G. Hotte, M. Soulard (HQ), L. Leung (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997Modelling Methodology for Obstructions in the sub-channel Code ASSERT IV"P. White, R.F. Dam, M.R. Soulard, N. Lee (AECL)" Niagara-on-the-Lake
20th Nuclear Simulation Symposium1997High Heat-Flux Transfer and Pressure Drop Correlations for Reactor Thermalhydraulic Simulations"D.R. Novog (MacU), S.T. Yin, J.S. Chang (AECL)" Niagara-on-the-Lake
21st Nuclear Simulation Symposium2000Updating OSV and CHF Correlations in NUCIRC for Pressure Tube Diametral Creep"B.D.J. Smith, G.D. Harvel (AECL)" Ottawa
21st Nuclear Simulation Symposium2000"Forty Years Since the Phrase ""Finite Element Method"" has been Coined"C. Manu (AECL) Ottawa
21st Nuclear Simulation Symposium2000Fluid to Fluid Modeling of Critical Heat Flux in CANDU Fuel Bundles"L.K.H. Leung, D.C. Groeneveld (AECL)" Ottawa
21st Nuclear Simulation Symposium2000Simulation of Critical-Heat-Flux Enhancement in Fuel Bundles by Tubes Equipped with Inserts"S.S. Doerffer, D.C. Groeneveld (AECL)" Ottawa
21st Nuclear Simulation Symposium2000The Effect of an Outer-Element Bow on Dryout Power and Post-Dryout Heat Transfer of CANDU Fuel BundlesS.C. Sutradhar (AECL) Ottawa
21st Nuclear Simulation Symposium2000Availability of Heavy Metals and Radionuclides in Soils Amended with Phosphate RocksI.A.A. Saad (U of Malaya) Ottawa
21st Nuclear Simulation Symposium2000A Script for the Automated Coupling of Neutronics and Thermalhydraulics Codes for the Simulation of Fast TransientsR.D. McArthur (AECL) Ottawa
21st Nuclear Simulation Symposium2000Fuzzy Adaptive Robust Optimal Controller for Wide Range Power Regulation of Nuclear Reactors"M.N. Khajavi (Azad U Takistan Branch), M.B. Menhaj, A.A. Suratgar (The Amir-Kabir U of Technology)" Ottawa
21st Nuclear Simulation Symposium2000CANDU 6 Zone Control Units EfficiencyG.M. Toma (Cernavoda) Ottawa
21st Nuclear Simulation Symposium2000Validation of 3-Dimensional Neutron-Transport Calculations of CANDU Reactivity Devices"M. Ovanes, J.V. Donnelly (AECL)" Ottawa
21st Nuclear Simulation Symposium2000Characterization of a Thermalhydraulics Model for the Gentilly-2 PHTS"G.D. Harvel, M.R. Soulard (AECL), G. Hotte (HQ)" Ottawa
21st Nuclear Simulation Symposium2000Assessment of a Wolsong 1 PHTS Thermalhyraulic Model Based upon Site Data"H. Choi (KEPRI), L. Chrobak, G.D. Harvel (AECL), Y.B. Kim (KEPRI)" Ottawa
21st Nuclear Simulation Symposium2000Flow Verification and Flow/Power Characterization of a Commissioning Reactor Using Site Data and NUCIRC Code"P.M. White, G.D. Harvel (AECL)" Ottawa
21st Nuclear Simulation Symposium2000Validation of CATHENA MOD-3.5c/Rev. 0 For Single-Phase Water HammerT.G. Beuthe (AECL) Ottawa
21st Nuclear Simulation Symposium2000New Relationships for Two-Phase Turbulent Mixing in Rod Bundles"L.N. Carlucci, N. Hammouda (AECL), D.S. Rowe (D.S. Rowe and Associates)" Ottawa
21st Nuclear Simulation Symposium2000Assessment of the Use of Passive Autocatalytic Recombiners for Hydrogen Control in Future CANDU 6 ReactorsA. McGee (AECL) Ottawa
21st Nuclear Simulation Symposium2000Validation of the MODTURC_CLAS Moderator Circulation Code for CANDU 9 Steady-State and Transient Conditions"L.N. Carlucci, V. Agranat, G.M. Waddington, H.F. Khartabil, J. Zhang (AECL)" Ottawa
21st Nuclear Simulation Symposium2000Three-Dimensional Moderator Circulation Experimental Program for Validation of CFD Code MODTURC_CLAS"H.F. Khartabil, W.W.R. Inch (AECL), J. Szymanski, D. Novog, V. Tavasoli, J. Mackinnon (OPG)" Ottawa
21st Nuclear Simulation Symposium2000Simulator Validation of Calculation Code in Rednet Upgrade SystemT. Qian (AECL) Ottawa
21st Nuclear Simulation Symposium2000Thermalhydraulic Assessment of the Pickering NGS ÊB∆ Feed and Bleed System for the Hot Boiler Chemical Clean (Siemens Process)C.M. Larencez (OPG) Ottawa
21st Nuclear Simulation Symposium2000ROP Analysis Update based on recent NUCIRC Code Validation on Commissioning and Actual Data at Cernavoda NPPN. Mazalu (Cernavoda) Ottawa
22nd Nuclear Simulation Symposium2002Coolant Void Reactivity Coefficient In a CANDU: A 2-D Transport-Diffusion Comparison"G. Marleau, E. Varin (EPM)" Ottawa
22nd Nuclear Simulation Symposium2002HELIOS/DRAGON/NESTLE Codes∆ Simulation of Void Reactivity in a CANDU Core"H.N. Sarsour, F. Rahnema, S. Mosher (NazConsulting), P.J. Turinsky (North Carolina State U), D. Serghiuta (CNSC), G. Marleau, T. Courau (EPM)" Ottawa
22nd Nuclear Simulation Symposium2002Assessment of Void Reactivity Effect in Heavy Water Moderated Reactor"B-J Min, G. Roh, K.J. Yoo (KAERI), S-K Oh (Ajou U)" Ottawa
22nd Nuclear Simulation Symposium2002Comparison Of Selected Film Boiling Heat Transfer Prediction Methods With The Data Bank"Y. Guo1, D.C. Groeneveld, A. Vasic, L.K.H. Leung, S.C. Cheng (AECL, UO)" Ottawa
22nd Nuclear Simulation Symposium2002Turbulent Friction Factor Correlation for Bare Rod Bundle in a Hexagonal Duct"K-W Seo, D-H Hwang, S-Q Zee (KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002Methodology to Assess the Transient Contact Heat Transfer Coefficient between Pressure Tube and Calandria Tube Using Contact Boiling Test Data"H.Z. Fan, M. Shams, D.B. Sanderson (AECL)" Ottawa
22nd Nuclear Simulation Symposium2002A Study on CANDU Model Assessment of RELAP5/CANDU using RD-14M B9401 Multi-channel RIH Break Experiment"Y.J. Cho, I.G. Kim, S. Lee, Y.S. Bang (KINS)" Ottawa
22nd Nuclear Simulation Symposium2002An Assessment of Prediction Methods Incorporating the Effect of Axial Heat Flux Distribution on Subchannel Critical Heat Flux in CANFLEX Bundles"U.P.M. Senaratne, V.C. Frisina (AECL)" Ottawa
22nd Nuclear Simulation Symposium2002Enhancement of Turbulent Heat Transfer Performance in Rod Bundle Subchannel by Large Scale Vortex Flow Generation"J-S Park, K. Chun, Y-D Choi (KINS)" Ottawa
22nd Nuclear Simulation Symposium2002The Film Boiling Look-Up Table: An Improvement In Predicting Post-CHF Temperatures"D.C. Groeneveld (AECL), L.K.H. Leung, A.Z. Vasic, Y.J. Guo (UO), M. El Nakla (AECL), S.C. Cheng (UO)" Ottawa
22nd Nuclear Simulation Symposium2002A Prediction Method For The Effect of Radial Heat-Flux Distribution On Critical Heat Flux In CANFLEX BundlesL.K.H. Leung (AECL) Ottawa
22nd Nuclear Simulation Symposium2002A Monte Carlo-Based Estimate of the Diffusion Coefficient in a CANDU Cell"G. Ilas, F. Rahnema, S. Mosher (Georgia Institute of Technology), G.W. Woodruff (School of Mechanical Engineering, Atlanta), R. Stamm'ler (Studsvik Scandpower AS)" Ottawa
22nd Nuclear Simulation Symposium20023D Heterogeneous Transport Calculations of CANDU Fuel with EVENT/HELIOS"Farzad Rahnema, S. Mosher, D. Ilas (Georgia Institute of Technology), G.W. Woodruff (School of Mechanical Engineering), C. de Oliveira, D. Matthew (Imperial College of Science, Technology and Medicine), R. Stamm'ler (Studsvik Scandpower AS, Norway)" Ottawa
22nd Nuclear Simulation Symposium2002Benchmark of WIMS-IST Against MCNP for CANDU Pressure Tube Fast Fluxes"R.E. Donders, S.R. Douglas (AECL)" Ottawa
22nd Nuclear Simulation Symposium2002A New Method for Multigroup Cross Sections Calculation"I.K. Attieh, R.E. Pevey (U of Tennessee)" Ottawa
22nd Nuclear Simulation Symposium2002Nuclear Reactor Conceptual Design: Methodology for Cost-Effective Internalisation of Nuclear Safety"M. Gimenez, P. Grinblat, M. Schlamp (CNEA, Argentina)" Ottawa
22nd Nuclear Simulation Symposium2002HELIOS/DRAGON/NESTLE Codes∆ Simulation of the Gentilly-2 Loss of Class 4 Power Event"H.N. Sarsour (Independent Consultant), P.J. Turinsky (Dept of Nuclear Engineering North Carolina State U)" Ottawa
22nd Nuclear Simulation Symposium2002Bruce A Restart Initial Core Loading"C. Ngo-Trong (AECL), R.E. Sunderland (National Nuclear Corporation Limited, UK)" Ottawa
22nd Nuclear Simulation Symposium2002SIMBRASS and Neutron Overpower Analysis"M. Levine, L. Blake, E. Attia (OPG)" Ottawa
22nd Nuclear Simulation Symposium2002LOCA Analysis for the Basic Design of HANARO Fuel Test Loop"D-Y Chi, C-Y Lee, B-S Sim, J-Y Kim, C. PARK (HANARO Center, KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002Development of MARS-h for Hanaro Safety Analysis"C. Park, H-I Kim, G-Y Han, W-J Lee, G-S Ha (HANARO Center, KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002Effect Of Radial Heat Flux Distribution On Pressure Drops"M.K.Y. Ip, U.P.M. Senaratne, L.K.H. Leung, (AECL)" Ottawa
22nd Nuclear Simulation Symposium2002How Simulation Improves Design"A.S. Doval (INVAP SE, Argentina)" Ottawa
22nd Nuclear Simulation Symposium2002Impact Strength Analysis of CANFLEX Fuel During CANDU-6 Normal Refueling"M-S Cho, H. Chun Suk (KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002A New Cognitive HRA Analysis using System Dynamics"M. Jae (Hanyang U, Korea)" Ottawa
22nd Nuclear Simulation Symposium2002The Role of a True Value in Monte Carlo Uncertainty Analyses with Application to BEAU MethodologyP. Sermer (NSS) Ottawa
22nd Nuclear Simulation Symposium2002Effectiveness of Setback in Liquid-Zone-Control Pump FailureP. Schwanke (AECL) Ottawa
22nd Nuclear Simulation Symposium2002Three-Dimensional Analyses of Fluid Flow and Heat Transfer for Moderator Integrity Assessment in PHWR"S.O. Yu, M. Kim, B.S. Kim, H.J. Kim (KINS), K.H. Bang (Korea Maritime U)" Ottawa
22nd Nuclear Simulation Symposium2002CFD Model Development and Validation for High Pressure Liquid Poison Injection for CANDU-6 Shutdown System No. 2"B.W. Rhee, C.J. Jeong (KAERI), H.J. Yun, D.S. Jang (Choongnam National U)" Ottawa
22nd Nuclear Simulation Symposium2002Steady State 3-D Simulation of CANDU6 Moderator Circulation Under the Normal Operating Condition"C. Yoon, B.W. Rhee, B.J. Min (KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002SLOWPOKE Integrated Reactor Control and Instrumentation System (SIRCIS) for Operation and Simulation"L.R. Cosby, L.G.I. Bennett, K.S. Nielsen, R.G.V. Hancock (CMRC/RMCC)" Ottawa
22nd Nuclear Simulation Symposium2002Estimating Signal Dynamics Of Safety And Regulating Systems Using Reactor Noise AnalysisO. Glockler (NSS) Ottawa
22nd Nuclear Simulation Symposium2002Estimating The Prompt Fractions Of In-Core Flux Detectors In Reactor Trip MeasurementsO. Glockler (NSS) Ottawa
22nd Nuclear Simulation Symposium2002SDS-2 Modelling with DRAG_SHELLM. Boubcher (AECL) Ottawa
22nd Nuclear Simulation Symposium2002Porting RFSP-IST From HP-UX Platform to PC Platform"I. Patrulescu, I. Dumitrache, W. Shen, D.A. Jenkins (AECL)" Ottawa
22nd Nuclear Simulation Symposium2002Least-Squares Fitting Method for On-Line Flux mapping of CANDU-PHWR"I.S. Hong, C.H. Kim (Seoul National U), H.C. Suk (KAERI)" Ottawa
22nd Nuclear Simulation Symposium2002A Feasibility Study on CANFLEX-RU 4-Bundle Shift Scheme in CANDU-6 Reactor"H.C. Suk, S.Y. Kim, C.K. Jo (KAERI)" Ottawa
23rd Nuclear Simulation Symposium2008Multiphysics Software and the Challenge to Validating Physical ModelsJ. Luxat (MacU) Ottawa
23rd Nuclear Simulation Symposium2008Enhancement of Critical Heat Flux in CANDU Fuel Bundles - A Review of the Past 45 Years"D. Groeneveld (UO, AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Licensing Nuclear Reactors in Canada Recent Changes to the CNSC ApproachT. Jamieson (CNSC) Ottawa
23rd Nuclear Simulation Symposium2008Refurbishment of Point Lepreau Generating Station"P.D. Thompson, Bruce Willemsen, T. Chapman, D. Mullin (NBP), R. Jaitly, L. Comanescu, A. Ranger (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Energy and Spatial Dependence of MCNP Simulations for ZED-2 Critical ExperimentsK. Kozier (AECL) Ottawa
23rd Nuclear Simulation Symposium2008A Premilinary Study of the OECD/NEA 3D Transport Problem Using the Lattice Code DRAGON"N. Martin, G. Marleau, A. H?bert (EPM)" Ottawa
23rd Nuclear Simulation Symposium2008Using Environment Dependent Cell Properties for ACR-1000 Core Calculations"J.-S. Duquette, G. Marleau, R. Chambon (EPM)" Ottawa
23rd Nuclear Simulation Symposium2008Revision of the Fuel Management Studies of the Atucha-2 Reactor. Implementation of An Automatic Refuelling Simulation Program"R. Mollerach, M. Higa, M. Silva, J. Fink (Nucleoel?ctrica Argentina S.A.)" Ottawa
23rd Nuclear Simulation Symposium2008Application of Simulated Annealing to Determining RFSP Target Exit Irradiations"P.D. Buchan (OPG), C. Stewart (UW)" Ottawa
23rd Nuclear Simulation Symposium2008Verifying Control Logic Specification Using Mathematical Modeling and Dynamic Simulations"J. Perras (AECL), A. Xing, J. Harber (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Revised Delayed Neutron Data for Pickering NGS B"C. Stewart (UW), P.D. Buchan (OPG)" Ottawa
23rd Nuclear Simulation Symposium2008Multiscale Modelling of Creation and Evolution of Defects in SiC Diode Detectors Placed At A Neutron Field"B. Khorsandi (Candesco), T. Blue, W. Windl (Ohio State University)" Ottawa
23rd Nuclear Simulation Symposium2008Standalone Visualization Tool for Three-Dimensional DRAGON Geometrical Models"A. Lukomski, B. McIntee, D. Moule, E. Nichita (UOIT)" Ottawa
23rd Nuclear Simulation Symposium2008Verification of the Cross-Section and Depletion Chain Processing Module of DRAGON 3.06"R. Chambon, G. Marleau (EPM), A. Zkiek (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Dynamic Simulation of A CANDU 6 Reactor"M. Borairi, J. Tseng, M. Fonooni, P. Zahedi (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008The Design Process and Simulation Tools Used in the Neutronic Design of the ACR-1000 CoreA. Buijs (AECL) Ottawa
23rd Nuclear Simulation Symposium2008Investigation of Time-Averaged Channel Powers Versus Channel Powers From Time-Averaged Bundle Burnups"G. Wang (BP), F. Shanes (NSS)" Ottawa
23rd Nuclear Simulation Symposium2008Simulation of Three-Dimensional Loss-of-Regulation Transients in ACR-1000 Reactors"J. Hu, I. Martchouk, R. Robinson, M. Ovanes, A. Buijs (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Application of GRS Methodology to Coolant Void Reactivity Uncertainty Analysis in the ACR-1000"A. Colton, A. Connolly, M. Ovanes (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Development and Verification of the CATHENA GUIT. Chin (AECL) Ottawa
23rd Nuclear Simulation Symposium2008System-Level Validation of CATHENA Mod-3.5D for Early Blowdown Phase of Large LOCA ˚ RD-14M Tests B0405-B0413"J.W. Gu, G. McGee (AECL)" Ottawa
23rd Nuclear Simulation Symposium2008CATHENA Model of the End Shield Cooling System for Point Lepreau Generating Station"F. Caracas (AECL), M. Maltchevski (AECL), V. Lau, L. Sun (NSS)" Ottawa
23rd Nuclear Simulation Symposium2008Unsteady Reynolds Averaged Navier-Stokes: Toward Accurate Predictions in Fuel- Bundles and T-Junctions"E. Merzari, H. Ninokata (Tokyo Inst of Technology), E. Baglietto (CD-Adapco)" Ottawa
23rd Nuclear Simulation Symposium2008Development and Validation of the Shutdown Cooling System CATHENA Model for Gentilly-2"H. L?cuyer, C. Hasnaoui (Nucl?onex Inc.), G. Sabourin (AECL), S. Chapados (HQ)" Ottawa
23rd Nuclear Simulation Symposium2008An Accurate Method of Assessing Tube Wall Thickness Based on Flow Boiling and Single Phase Heat Transfer Measurements"A. Tanase (UO), D. Groeneveld (UO, AECL)" Ottawa
23rd Nuclear Simulation Symposium2008Parallelization of Neutron Transport Approximation Via Monte Carlo"F. Ali (UOIT), E. Waller (UOIT)" Ottawa
23rd Nuclear Simulation Symposium2008PHYSICSSHELL: A Solution to Multi-Code Linking"J. Szymandera (NSS), L. Blake (NSS), B.G. Phan (OPG), O. Nainer (BP)" Ottawa
23rd Nuclear Simulation Symposium2008Activity Modeling for Qualitative and Quantitative Fault Simulation of Nuclear Power PlantsH. Gabbar (UOIT) Ottawa
23rd Nuclear Simulation Symposium2008WIMS-IST/DRAGON-IST Side-Step Calculation of Reactivity Device and Structural Material Incremental Cross Sections for Wolsong NPP Unit 1"M. Dahmani, R. McArthur (AECL), B.G. Kim (KOPEC), S.M. Kim (NETEC/KHNP), H.-B. Seo (KHNP)" Ottawa
23rd Nuclear Simulation Symposium2008"Analysis of September 2007, Bruce A Unit 3 SDS1 Rundown to Assess the Impact of Empty Channels on Detector Responses""O. Nainer (BP), C. Banica (OPG)" Ottawa
23rd Nuclear Simulation Symposium2008Comparison Between COMSOL and RFSP-IST for a 2-D Benchmark ProblemG. Gomes (AECL) Ottawa
23rd Nuclear Simulation Symposium2008Validation of CERBRRS Against Gentilly-2 Station Data"E. Varin, J. Mao (AECL), S. Kaveh (HQ), A. Baudouin (Nucl?onex Inc.)" Ottawa