Canadian Nuclear Society
Nuclear Simulation Symposium
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| Conference | Year | Title | Author | Location |
|---|---|---|---|---|
| 13th Nuclear Simulation Symposium | 1987 | "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 Symposium | 1987 | CONIFERS - A Reactor Core Analysis Program with Emphasis on Reactors with Channels | R.S. Davis (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Lattice Characteristics that Influence the Change in Reactivity with Coolant Voiding in CANDU Lattices | J. Griffiths (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Choking Criterion for One-Dimensional Critical Multiphase Flow in Ducts and Open Channels | "M. Dostie, Y. Mercadier (U de Sherbrooke)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Assessing Spatial Effects in Aerosol Transport Models | M. Razzaghi (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Analysis 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 Symposium | 1987 | Investigation of Countercurrent Flooding Phenomena in Vertical-to-Inclined Elbows of Varying Angle | "C.P. Tingle, M. Kawaji (UT)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | REGIME-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 Symposium | 1987 | Numerical Modelling of Phase Distribution in Interconnected Subchannels | "J.C. Kiteley, M.B. Carver, A. Tahir (AECL)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Radionuclide 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 Symposium | 1987 | Darlington 'A' Real Time Simulation | "P. Archer (AECL), E. Hung (OH)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Real 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 Symposium | 1987 | Running 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 Symposium | 1987 | PCTRAN/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 Symposium | 1987 | A Simple Steam Generator Model for Plant Optimization Studies | "N.J. Spinks, M.R. Soulard (AECL)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Characteristics 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 Symposium | 1987 | A Simple Flow Stability Model for Figure-of-Eight Loop with Outlet Header Interconnect | P. Gulshani (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Two-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 Symposium | 1987 | Small Inlet Header Break Experiments in RD-14 | "G.R. McGee, F.W. Barclay (AECL)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Error Bounds on the Solutions of Parabolic Differential Equations | S.R. Vatsya (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | The Allure of R-Functions | "S.R. Douglas, M.S. Milgram (AECL)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | A Comparison of the Rate Form of the Equation of State to the Jacobian Form | W.J. Garland (MacU) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | "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 Symposium | 1987 | Numerical Simulation of Phase Redistribution Caused by Obstructions and Bends | "M.B. Carver (AECL), M. Salcudean (UBC)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Simulating 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 Symposium | 1987 | Thorium-Fuelled CANDU Nuclear Reactor Optimal Fuel Management at Approach to Refuelling Equilibrium | H.W. Bonin (RMC) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | The Role of Enriched Fuel in CANDU Power Uprating | "P.S.W. Chan, A.R. Dastur (AECL)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Predicting Creep Response of CANDU Fuel Channel Assemblies | R.G. Sauve (OH) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | A Preprocessor for CDEPTH Input File Preparation | "C.O. Poidevin, J. Tennant (OH)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | In-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 Symposium | 1987 | Irradiation-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 Symposium | 1987 | Modelling the Steam Temperature Distribution in CATHENA and Its Application to Pressure Tube Circumferential Temperature Distribution Analysis | C.B. So (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | NUCCP (NUCIRC) Predictions of Channel Flow and Comparison with Site Measurements at the Point Lepreau Generating Station | W.J. Hartmann (AECL) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | The Phenomenology of the PHT Pump Trip Events | "G. Delorme, (Groupe d'Analyse Nucleaire), L.J. Watt (IDEA Research)" | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | SOPHT Simulation of Valve Failures in the Heat Transport System of Bruce NGS-B | D. Zobin (OH) | Chalk River |
| 13th Nuclear Simulation Symposium | 1987 | Simulation of ECCS Performance Using FIREBIRD III Mod. 1 | "V.Q. Tang, Q.S. Truong (AECB)" | Chalk River |
| 14th Nuclear Simulation Symposium | 1988 | Transdec: 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 Symposium | 1988 | A Universal Driver for Collision Probability and Response Matrix Transport Codes | "G. Marleau, A. Hebert (EPM)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | From Platinum to Mercury: The Alchemist's Nightmare | "K.J. Serdula, G. Parent (Serdula Systems)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Calculating Three-Dimensional Neutronic Transients on Microcomputers | "B. Rouben, C.R. Calabrese (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | A Method for Simulating Grey Slabs in CANDU Reactors | "A.R. Dastur, D.B. Buss (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | DERREP; 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 Symposium | 1988 | Simple Functions for the Fast Approximation of Light Water Thermodynamic Properties | "W.J. Garland, B.J. Hand (MacU)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Piecewise Polynomial Approximation of Thermodynamic Properties of Heavy Water | "Y. Liner, B.N. Hanna, D.J. Richards (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Modelling of Nonhomogeneous Nonequilibrium Critical Two-Phase Flow | S.M. Sami (U of Sherbrooke) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Numerical Predictions of Two-Phase Flow Parameters in Inverted U-tubes under Reflux Condensation | "R. Girard, J.S. Chang (MacU)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Investigation of CCFL in Pipe Elbows | "L. Thomson, M. Kawaji, V.S. Krishnan (UT)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Prediction of Pressurizer Transient by the IDRIFF Two-phase Simulation Code | "R. Sollychin, J.S. Chang, W.J. Garland (MacU)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | The Dynamic Simulation of a Two-Node Non-Equilibrium 600MW CANDU Pressurizer System | "H.O. Tezel, D.A. Meneley (UNB)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | MISSFINCH: Models for Steady Stratified Flow in CANDU Headers | P. Gulshani (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Steady-State Two-Phase Header Flow Model | "H.G.O. De Man, Y. Feyginberg, W.I. Midvidy (OH)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | GENHTP - A New Heat Transfer Package for CATHENA | "J.P. Mallory, P. Yuen, C.B. So (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Reactor Operator Companion for CANDU Heat Transport Systems | "W.J. Garland, J.W.D. Anderson, J.D. Hoskins (MacU)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | CATHENA Study of Large LOCA Channel Behaviour | "S.D. Grant, R.L. Dasilva (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | The 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 Symposium | 1988 | Large Outlet Header Break Experiments in a CANDU-Type Heat Transport Loop | P.J. Ingham (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Implementation of a Post-Dryout Model in the ASSERT Subchannel Code | "A. Tahir, S. Robinovitch, P.R. Thibeault (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Thermalhydraulic Plant Modelling of a CANDU Reactor Including Plant Control Systems using CATHENA | "F.W. Barclay, D.J. Richards (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Safety Aspects of Nuclear Battery Reactor Design | J.V. Donnelly (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Some Aspects of MAPLE-10 Fuel Performance During Normal Operation | "S. Girgis, I.E. Oldaker, G.E. Gillespie (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Recent 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 Symposium | 1988 | "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 Symposium | 1988 | The Sensitivity of MAPLE-X10 Core Reactivity to Variations in the Three-Dimensional Coolant Void Distribution | H.J. Smith (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Upper Bound Calculations of Aerosol Vapour Mass Concentrations in a CANDU Fuel Channel during Severe Fuel Damage Accidents | S.R. Mulpuru (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Pressure Challenges to CANDU Containment due to Hydrogen Combustion during Accidents | P. Klazek (OH) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | A Solution Scheme for Aerosol Transport Models | "S.R. Vatsya, M. Razzaghi (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Integrated Aerosol and Thermalhydraulic Modelling | B.H. McDonald (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Effects of Antivibration Bars on the U-Bend Flow Distribution in Recirculating Steam Generators | "L.N. Carlucci, J.M. Pietralik (AECL)" | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | "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 Symposium | 1988 | Simulation of the SPEL Small Scale Moderator Experiments Using the General Purpose Fluid-Flow Heat Transfer Code Phoenics | W.M. Collins (AECL) | Pinawa |
| 14th Nuclear Simulation Symposium | 1988 | Thermalhydraulic Simulations for Plate-Type Nuclear Fuel Elements | "H.E.C. Rummens, J.S. Chang, P. Ernst (MacU)" | Pinawa |
| 15th Nuclear Simulation Symposium | 1988 | Natural Circulation Experiments in the RD-14 Multiple Channel Thermohydraulics Loop | "P.J. Ingham, J.P. Mallory (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Comparison 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 Symposium | 1988 | Small 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 Symposium | 1988 | Analysis of Critical Inlet Header Break LOCA Experiments in the RD-14 Test Facility | "N.K. Popov, G.R. McGee (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Enhanced 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 Symposium | 1988 | Modelling 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 Symposium | 1988 | SPORTS-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 Symposium | 1988 | Reactivity 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 Symposium | 1988 | Preliminary Thermohydraulics Analysis of the AMPS-1000 Reactor Core Using COBRA-1 V | A. Tahir (ECSPS) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Application 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 Symposium | 1988 | The Analysis with Code TANK of a Postulated Reactivity-Insertion Transient in a 10-MW MAPLE Research Reactor | R.J. Ellis (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | An 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 Symposium | 1988 | Analysis 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 Symposium | 1988 | "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 Symposium | 1988 | Improvement and Testing of a CANDU Pressurizer Dynamics Simulation | "J.S. Pitre, D.A. Meneley (UNB)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Real-Time Simulation of PHT Pump Low-Speed Drives for the Bruce NGS-B Training Simulator | F. Capogreco (OH) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Verification of the TUF Code Against the JUICE 1976 Standard Problems | "A. Tomasone, W. Liu, J.C. Luxat (OH)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Obtaining POWDERPUFS Ceil Cross Sections from WIMS | M. Gold (OH) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Calculation of Device Static Reactivity Worth by Modal Analysis | "M. Gold, M.Z. Farooqui, N. Roy (OH)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Reactivity Transient Due to Malfunction of a Mechanical Zone Controller in the CANDU-3 Reactor | V.K. Mohindra (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | A Space-Time Reactor Simulation | "G. Gaboury, W.J. Garland (MacU)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | "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 Symposium | 1988 | A Method for Calculation of Incremental Cross Sections for Rod-and-Tube Type Adjusters | "S.D. Arguner, A.U. Rehman (OH)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | "A Fully Implicit, Back-Substituted Algorithm for Thermalhydraulic Networks" | "R.J. Wilson (EACS Inc), W.J. Garland (MacU)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Real-Time Simulation of CANDU Heat-Transport System | "J.D. Hoskins, W.J. Garland (MacU)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | An Iterative Method to Solve Large Sparse Lineal Systems | S.R. Vatsya (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Parity Simulation Applied to Reactor Physics Nodal Theory Transient Analysis | P.J. Laughton (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Calculating Array Criticality Using Thomas's Limiting Surface Density Model | J.W. Thompson (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | An Analytical Solution to the Equations for Long-Term Transport and Release of Fission Products | K.R. Weaver (Shaftesbury Scientific Limited) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Recent 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 Symposium | 1988 | CATHENA Prediction of MAPLE-X10 Performance During a Complete Pipe Severance | "T.E. MacDonald, S.Y. Shim (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Investigation of Refilling Behaviour of a Simulated CANDU Feeder Pipe | "R. Thuraisingham, M. Kawaji (UT), J.C. Luxat (OH)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | MAPL3D 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 Symposium | 1988 | A Model for Two-Phase Redistribution in Dividing Two-Phase Flow | "J.D. Ballyk, M. Shoukri (MacU)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Power 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 Symposium | 1988 | The 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 Symposium | 1988 | RFSP Simulation of a Reactor-History Slice Featuring Saturated Zone-Control Compartments | "M.A. Dencer, B. Rouben (AECL), E. Young (NBEPC)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | CANDU 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 Symposium | 1988 | Reactor Physics Simulation of Fast Reactivity Transients in the Nuclear Battery | J.V. Donnelly (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | SIMEX-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 Symposium | 1988 | Application 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 Symposium | 1988 | PRESCON2 Simulation of the OECD/CSNI Containment International Standard Problem #23 | "W.M. Collins (AECL), R.A. Gibb (NBEPC)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Assessment of FFTF/MOTA and Thermal Reactor Irradiation Facilities for Advanced Tritium-Breeder-Material Tests | R.E. Donders (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | An Overview of Ontario Hydro's Nuclear Risk Assessment Program | V.M. Raina (OH) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Real-Time Simulation of Electrical Distribution Systems | "A. Abramovitch, N. Kratsios (CAE)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | CIRENE Fuel Bundle Integrity Following a Feeder Break | "P.N. Singh, R. Sejnoha, M. Tayal (AECL), G. Valli (ENEA)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Transient Thermal Analysis of an Idealized Fuel Element | "G.R. McGee, J.W. DeVaal (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | An Improved Model for the Release of Fission Gas in CANDU Fuel | "M. Tayal, A. Ranger (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Influence of Pellet. Shapes on Sheath Strains: ELESTRES Predictions vs Irradiation Measurements | "N.C. Singhal, M. Tayal, T.J. Carter (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Heat 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 Symposium | 1988 | Simulation of a Closed Two-Phase Thermosiphon with the CATHENA Code | "B.N. Hanna, B.G. Taylor (AECL)" | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | A Method of Predicting CHF in Interconnected Subchannels | C.W. Snoek (AECL) | Mississauga |
| 15th Nuclear Simulation Symposium | 1988 | Two-Phase Pressure Drop Across Flow Obstructions | S.C. Sutradhar (AECL) | Mississauga |
| 16th Nuclear Simulation Symposium | 1991 | Inclined Feeder Refill Tests Conducted in the Cold Water Injection Test Facility - Analysis and Implications | P.T. Wan (OH) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Validation 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 Symposium | 1991 | Critical Break Experiments in the RD-14M Thermalhydraulics Test Facility | "A.J. Melnyk, P.J. Ingham, T.V. Murray" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | A 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 Symposium | 1991 | Non-Linear Geometries of Continuous - Time Reactor Dynamics | A.S. Adebiyi (OH) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Power Feedback Effects in the SMOKIN Code | M. Gold (OH) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | NEACRP 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 Symposium | 1991 | Comparison 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 Symposium | 1991 | Experimental 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 Symposium | 1991 | ASSERT-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 Symposium | 1991 | SOPHT-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 Symposium | 1991 | Experimental Study of Convective Mass Transfer Rates Using an Evaporative Mass Transfer Technique in Obstructed Channels | T.S. Balint (OH) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Some Aspects of the Criticality Safety Analysis of a Fissile Solution Storage Tank | J.W. Thompson (ANSL) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Reactivity 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 Symposium | 1991 | Optimization of a New Flux-Mapping Detector Layout for the CANDU 6 Reactor | "K. Ossia, C.M. Bailey (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Accuracy of the Improved Quasistatic Method as Applied to CANDU Transient Analysis | "P.S.W. Chan, A. Dastur (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Simulation 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 Symposium | 1991 | Modelling 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 Symposium | 1991 | Recent 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 Symposium | 1991 | Parallel 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 Symposium | 1991 | Comparison 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 Symposium | 1991 | Commissioning 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 Symposium | 1991 | Real Time Simulation of the Point Lepreau Boiler | "J. Salim, G. Salim (CAE)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Mass Conservative Hydraulic Network Solver | J. Pitre (UNB) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | A Graphic Interface for DSNP | "H.G. Noye, J. Pitre (UNB)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | The Secondary Side of DSNP | "N. Arbeau, D.A. Meneley (UNB)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Display of RD-14M Data With IsoVu | "J.B Hedley, R.S. Swartz (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Pre and Post-Processing CATHENA Simulations | "S.D. Grant, P.H. Ta (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | A Simulation Model for One-Dimensional Two Phase Flow | "J. Zhang, D.A. Meneley (UNB)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Radiative Heat Transfer in a Partially-filled CANDU Reactor Channel | "T. Taryo, E. Hussein (UNB)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | The 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 Symposium | 1991 | Modelling 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 Symposium | 1991 | Analysis 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 Symposium | 1991 | Simulation 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 Symposium | 1991 | Transition 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 Symposium | 1991 | Post-Dryout Behaviour During Flow Oscillations | "N.N. Wahba, A.P. Muzumdar (OH)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Automatic 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 Symposium | 1991 | Fuelling 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 Symposium | 1991 | Comparison 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 Symposium | 1991 | Passive Design Options for CANDU | "N.J. Spinks, J.T. Dunn, T.C. De Mello, S. Azeez (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Experimental 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 Symposium | 1991 | 3-D Simulation of Moderator Circulation For A Large Loss of Coolant Event | "V. Yee, W.M. Collins (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Using ELESTRESS and NUCIRC to Determine CCP Penalties Associated with Heavy Bundles | "A. Chan, B. Wong, A.M. Manzer (AECL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | An 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 Symposium | 1991 | Numerical 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 Symposium | 1991 | CREM - A New Thermalhydraulic Code for Containment Impairment Analysis | "J.O. Oyinloye, M.J. Lewis (Electrowatt), C.K. Scott (ANSL)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Process Fault Verification System | "P. Piumsomboon, D.A. Meneley, R. Girard (UNB)" | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Process Noise Based Monitoring and Diagnostics in Nuclear Power Plants | O. Glocker (UNB) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Applying Multivariate Autoregressive Modelling and Sequential Probability Ratio Test to Nuclear Power Plant Data | O. Glocker (UNB) | Saint John |
| 16th Nuclear Simulation Symposium | 1991 | Bulk Power Limits for the CANDU-6 Reactor | "J. Handbury (ANSL), C.W. Newman, E.G. Young (NBP)" | Saint John |
| 18th Nuclear Simulation Symposium | 1994 | The Use of Shell Scripts as Analysis Tools | "G.D. Gaboury (OH), H.J. Smith (Leathern-Smith Consulting)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Beyond Dragon | Alain Hebert (EPM) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | The 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 Symposium | 1994 | Towards 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 Symposium | 1994 | A Simplified Heterogeneous Bl Model with Isotropically-Reflected Neutrons on Assembly Boundary | "I. Petrovic, P. Benoist, G. Marleau (EPM)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Estimates of Void Reactivity Coefficients with MCNP and WIMS-AECL | M.S. Milgram (AECL) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | On the Calculation of Void Effect in CANDU Using a Lattice Cell Code | J. Whitlock (MacU) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Parametric Analysis of the DUPIC Fuel Cycle | "H. Choi, B. Rhee, H. Park (KAERI)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Experiments 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 Symposium | 1994 | Analysis of Substitution Experiments in ZED-2 with Physically Realistic Model Adjustments | R.S. Davis (AECL) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Simulation of the 1992 SDSl Trip Test at Point Lepreau | "D.A. Jenkins (AECL), E.G. Young (NBP)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Simulation of Reactivity Control Devices in a CANDU-6 Reactor Using DRAGON | "G. Marleau, R. Roy (EPM), B. Arsenault (AECB)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Predictions 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 Symposium | 1994 | Analysis of Passive Heat Transport for an Advanced CANDU Containment | "M. Krause, S. Jones, P.M. Mathew (AECL)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | ASSERT 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 Symposium | 1994 | ASSERT/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 Symposium | 1994 | Application 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 Symposium | 1994 | The Effect of Flow Transients on CHF at CANDU-Reactor Conditions | S.C. Sutradhar (AECL) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Sensitivity of the Primary Heat Transport System Behaviour to Different ECC Assumptions and to Different Pump Trip Delays Used During a Small Break Simulation | A.V. Galia (NBP) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Large Break Loss-of-Coolant Accidents Analysis Using the TUF Code | "R.Y. Chu, W.W. Yousef, W.C. Chan (OH)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Best 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 Symposium | 1994 | CANDU 6 and RD-14/RD-14M Thermosyphoning | M.R. Lin (AECL) | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Computer Simulation of Initiation of Detonation by Shock Focusing | "C.K. Chan, F. Torchia, A.M. Guerrero, J. Loesel Sitar (AECL)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | The Role of Simulation in CANDU 3 Fuel Handling Control System Design | "N.H. Brown, D. Arapakota (AECL)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Simulation 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 Symposium | 1994 | Simulation of 18O and 3H Distributions in the Atikokan Research Area | "D.U. Ophori, T. Chan (AECL)" | Pembroke |
| 18th Nuclear Simulation Symposium | 1994 | Sensitivity 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 Symposium | 1994 | Analysis of Bearing-Pad to Pressure-Tube Contact Heat Transfer | "T. Nitheanandan, Q.M. Lei, R.G. Moyer (AECL)" | Pembroke |
| 20th Nuclear Simulation Symposium | 1997 | The 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 Symposium | 1997 | On the Preparation of Library Data for an Implementation of the Method of Subgroups in WIMS-AECL | P.J. Laughton (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Calculation 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 Symposium | 1997 | An 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 Symposium | 1997 | History-Based Calculations Using WIMS-AECL in RFSP | "B. Arsenault, J.V. Donnelly, D.A. Jenkins (AECL)" | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | CATHENA Study of Two phase Water Hammer Inter-Peak Timing | T.G. Beuthe (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Preliminary Investigation of the Solution of Sparse Matrices in CATHENA | "T.G. Beuthe, J.B. Hedley (AECL)" | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Refill Effectiveness using High-Boiling Point Emergency Coolant | G.R. McGee (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Darlington 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 Symposium | 1997 | A 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 Symposium | 1997 | Analysis of the Fast Neutron Spectrum Inside the Materials Test Bundles in the NRU Loops | T.C. Leung (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Estimates of the Neutron Flux Distribution in an End-Fitting of the Bruce Unit 2 using Analog Monte-Carlo | M.S. Milgram (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Study 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 Symposium | 1997 | Validation 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 Symposium | 1997 | The Placement of Lateral Region in ID MTR Fuel Lattice Cell Models | "S. Day, W.J. Garland (MacU)" | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Photoneutron 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 Symposium | 1997 | An 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 Symposium | 1997 | Development 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 Symposium | 1997 | Optimisation of Operating Envelope and Safety Margin Using PRA Methods | "C. Stoica (Cernavoda), C.K. Scott (ANSL)" | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | A 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 Symposium | 1997 | Assessment 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 Symposium | 1997 | Numerical Schemes in CANSIM and Some Sensitivity Studies | V.I. Arimescu (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Fission 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 Symposium | 1997 | NUCIRC 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 Symposium | 1997 | Detailed 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 Symposium | 1997 | Modelling Techniques for Vanadium Detector Compensation | "J.C. Handbury (ANSL), C.W. Newman (NBP)" | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Dynamic Modelling for Shutdown-System-1 Depth Analysis | D.A. Jenkins (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Reactor Physics Simulation of the MNR January 1994 Fuelling Incident | H. Basha (MacU) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | Effect of Pressure Tube Creep on the Void Coefficient of a CANDU Fuel Bundle | M.S. Milgram (AECL) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | System 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 Symposium | 1997 | A 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 Symposium | 1997 | Development 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 Symposium | 1997 | Transient 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 Symposium | 1997 | CATHENA 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 Symposium | 1997 | Thermalhydraulics 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 Symposium | 1997 | Safety Analysis Uncertainty Related to Design and Manufacturing Quality Assurance | E.N. Sokolov (Siberian Directorate of Gosatomnadzor of Russia) | Niagara-on-the-Lake |
| 20th Nuclear Simulation Symposium | 1997 | A 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 Symposium | 1997 | Critical 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 Symposium | 1997 | Simulation 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 Symposium | 1997 | Modelling 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 Symposium | 1997 | High 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 Symposium | 2000 | Updating OSV and CHF Correlations in NUCIRC for Pressure Tube Diametral Creep | "B.D.J. Smith, G.D. Harvel (AECL)" | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | "Forty Years Since the Phrase ""Finite Element Method"" has been Coined" | C. Manu (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Fluid to Fluid Modeling of Critical Heat Flux in CANDU Fuel Bundles | "L.K.H. Leung, D.C. Groeneveld (AECL)" | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Simulation of Critical-Heat-Flux Enhancement in Fuel Bundles by Tubes Equipped with Inserts | "S.S. Doerffer, D.C. Groeneveld (AECL)" | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | The Effect of an Outer-Element Bow on Dryout Power and Post-Dryout Heat Transfer of CANDU Fuel Bundles | S.C. Sutradhar (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Availability of Heavy Metals and Radionuclides in Soils Amended with Phosphate Rocks | I.A.A. Saad (U of Malaya) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | A Script for the Automated Coupling of Neutronics and Thermalhydraulics Codes for the Simulation of Fast Transients | R.D. McArthur (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Fuzzy 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 Symposium | 2000 | CANDU 6 Zone Control Units Efficiency | G.M. Toma (Cernavoda) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Validation of 3-Dimensional Neutron-Transport Calculations of CANDU Reactivity Devices | "M. Ovanes, J.V. Donnelly (AECL)" | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Characterization of a Thermalhydraulics Model for the Gentilly-2 PHTS | "G.D. Harvel, M.R. Soulard (AECL), G. Hotte (HQ)" | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Assessment 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 Symposium | 2000 | Flow 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 Symposium | 2000 | Validation of CATHENA MOD-3.5c/Rev. 0 For Single-Phase Water Hammer | T.G. Beuthe (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | New 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 Symposium | 2000 | Assessment of the Use of Passive Autocatalytic Recombiners for Hydrogen Control in Future CANDU 6 Reactors | A. McGee (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Validation 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 Symposium | 2000 | Three-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 Symposium | 2000 | Simulator Validation of Calculation Code in Rednet Upgrade System | T. Qian (AECL) | Ottawa |
| 21st Nuclear Simulation Symposium | 2000 | Thermalhydraulic 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 Symposium | 2000 | ROP Analysis Update based on recent NUCIRC Code Validation on Commissioning and Actual Data at Cernavoda NPP | N. Mazalu (Cernavoda) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Coolant Void Reactivity Coefficient In a CANDU: A 2-D Transport-Diffusion Comparison | "G. Marleau, E. Varin (EPM)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | HELIOS/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 Symposium | 2002 | Assessment 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 Symposium | 2002 | Comparison 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 Symposium | 2002 | Turbulent 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 Symposium | 2002 | Methodology 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 Symposium | 2002 | A 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 Symposium | 2002 | An 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 Symposium | 2002 | Enhancement 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 Symposium | 2002 | The 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 Symposium | 2002 | A Prediction Method For The Effect of Radial Heat-Flux Distribution On Critical Heat Flux In CANFLEX Bundles | L.K.H. Leung (AECL) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | A 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 Symposium | 2002 | 3D 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 Symposium | 2002 | Benchmark of WIMS-IST Against MCNP for CANDU Pressure Tube Fast Fluxes | "R.E. Donders, S.R. Douglas (AECL)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | A New Method for Multigroup Cross Sections Calculation | "I.K. Attieh, R.E. Pevey (U of Tennessee)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Nuclear Reactor Conceptual Design: Methodology for Cost-Effective Internalisation of Nuclear Safety | "M. Gimenez, P. Grinblat, M. Schlamp (CNEA, Argentina)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | HELIOS/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 Symposium | 2002 | Bruce A Restart Initial Core Loading | "C. Ngo-Trong (AECL), R.E. Sunderland (National Nuclear Corporation Limited, UK)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | SIMBRASS and Neutron Overpower Analysis | "M. Levine, L. Blake, E. Attia (OPG)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | LOCA 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 Symposium | 2002 | Development 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 Symposium | 2002 | Effect 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 Symposium | 2002 | How Simulation Improves Design | "A.S. Doval (INVAP SE, Argentina)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Impact Strength Analysis of CANFLEX Fuel During CANDU-6 Normal Refueling | "M-S Cho, H. Chun Suk (KAERI)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | A New Cognitive HRA Analysis using System Dynamics | "M. Jae (Hanyang U, Korea)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | The Role of a True Value in Monte Carlo Uncertainty Analyses with Application to BEAU Methodology | P. Sermer (NSS) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Effectiveness of Setback in Liquid-Zone-Control Pump Failure | P. Schwanke (AECL) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Three-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 Symposium | 2002 | CFD 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 Symposium | 2002 | Steady 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 Symposium | 2002 | SLOWPOKE 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 Symposium | 2002 | Estimating Signal Dynamics Of Safety And Regulating Systems Using Reactor Noise Analysis | O. Glockler (NSS) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Estimating The Prompt Fractions Of In-Core Flux Detectors In Reactor Trip Measurements | O. Glockler (NSS) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | SDS-2 Modelling with DRAG_SHELL | M. Boubcher (AECL) | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Porting RFSP-IST From HP-UX Platform to PC Platform | "I. Patrulescu, I. Dumitrache, W. Shen, D.A. Jenkins (AECL)" | Ottawa |
| 22nd Nuclear Simulation Symposium | 2002 | Least-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 Symposium | 2002 | A 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 Symposium | 2008 | Multiphysics Software and the Challenge to Validating Physical Models | J. Luxat (MacU) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Enhancement of Critical Heat Flux in CANDU Fuel Bundles - A Review of the Past 45 Years | "D. Groeneveld (UO, AECL)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Licensing Nuclear Reactors in Canada Recent Changes to the CNSC Approach | T. Jamieson (CNSC) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Refurbishment 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 Symposium | 2008 | Energy and Spatial Dependence of MCNP Simulations for ZED-2 Critical Experiments | K. Kozier (AECL) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | A 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 Symposium | 2008 | Using Environment Dependent Cell Properties for ACR-1000 Core Calculations | "J.-S. Duquette, G. Marleau, R. Chambon (EPM)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Revision 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 Symposium | 2008 | Application of Simulated Annealing to Determining RFSP Target Exit Irradiations | "P.D. Buchan (OPG), C. Stewart (UW)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Verifying Control Logic Specification Using Mathematical Modeling and Dynamic Simulations | "J. Perras (AECL), A. Xing, J. Harber (AECL)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Revised Delayed Neutron Data for Pickering NGS B | "C. Stewart (UW), P.D. Buchan (OPG)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Multiscale 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 Symposium | 2008 | Standalone Visualization Tool for Three-Dimensional DRAGON Geometrical Models | "A. Lukomski, B. McIntee, D. Moule, E. Nichita (UOIT)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Verification 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 Symposium | 2008 | Dynamic Simulation of A CANDU 6 Reactor | "M. Borairi, J. Tseng, M. Fonooni, P. Zahedi (AECL)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | The Design Process and Simulation Tools Used in the Neutronic Design of the ACR-1000 Core | A. Buijs (AECL) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Investigation of Time-Averaged Channel Powers Versus Channel Powers From Time-Averaged Bundle Burnups | "G. Wang (BP), F. Shanes (NSS)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Simulation 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 Symposium | 2008 | Application of GRS Methodology to Coolant Void Reactivity Uncertainty Analysis in the ACR-1000 | "A. Colton, A. Connolly, M. Ovanes (AECL)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Development and Verification of the CATHENA GUI | T. Chin (AECL) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | System-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 Symposium | 2008 | CATHENA 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 Symposium | 2008 | Unsteady 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 Symposium | 2008 | Development 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 Symposium | 2008 | An 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 Symposium | 2008 | Parallelization of Neutron Transport Approximation Via Monte Carlo | "F. Ali (UOIT), E. Waller (UOIT)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | PHYSICSSHELL: A Solution to Multi-Code Linking | "J. Szymandera (NSS), L. Blake (NSS), B.G. Phan (OPG), O. Nainer (BP)" | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Activity Modeling for Qualitative and Quantitative Fault Simulation of Nuclear Power Plants | H. Gabbar (UOIT) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | WIMS-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 Symposium | 2008 | "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 Symposium | 2008 | Comparison Between COMSOL and RFSP-IST for a 2-D Benchmark Problem | G. Gomes (AECL) | Ottawa |
| 23rd Nuclear Simulation Symposium | 2008 | Validation of CERBRRS Against Gentilly-2 Station Data | "E. Varin, J. Mao (AECL), S. Kaveh (HQ), A. Baudouin (Nucl?onex Inc.)" | Ottawa |