Published: 1990-04-20

Articles

A Semi-Analytical, Inherently Parallel Method for LWR Thermal-Hydraulic Feedback

A.M. Ougouag, M. Vandermyde, B.G. Jones

568-571

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Mathematical Modelling of Material Transpon and Sludge Formation in Nuclear Steam Generators

Y. Liner, M.B. Carver, A.O. Campagna

572-593

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Parity Simulation of a Pressurized Water Reactor System

E.V. Depiante, J.E. Meyer

594-611

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Anti-Vibration Bar Model for the THIRST Computer Code''

A.O. Campagna, M.B. Carver

612-629

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Development of Square and Hexagonal Lattice Analysis Capability in WIMS-AECL

James V. Donnelly

630-646

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Generalization of the STAMM'LER Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries

Alain Hebert, Guy Marleau

647-649

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Interface-Flux Nodal Transpon Method

Peter Kohut

650-666

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Comparison of Monte Carlo and Interface Current Solutions to 3D Transpon Problems

Guy Marleau, R. Roy, Alain Hebert, E. Paradis

667-681

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Flow Regime Effects on the Neutronic Parameters of Liquid Metal-Gas Two-Phase Flow in a Fusion Reactor Coolant Channel

John C. Campeau, Jen-Shih Chang

682-705

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Image Processing for Neutron Radiography

Hon-Wei Syh, Raymond F. Saxe

706-715

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Thermalhydraulic Analysis of Containments

Mati Merilo, Thomas L. George

716-736

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Integrated Aerosol and Thermalhydraulics Modelling for CANDU Safety Analysis

B.H. McDonald

737-739

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Application-and Validation of the Pheonics Code for Moderator System Conditions in a CANDU Nuclear Generating Station

W.M. Collins, M. Garceau, M. El-Hawary

740-761

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Water Droplet Aerosol Removal by Flashing Jet Impingement

Hsu-Wen Chiang

762-765

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Thermal-Hydraulic Simulation of the Moderator System of Ontario Hydro's CANDU Reactors

K.J. Riffert, K.K. Fung, W.I. Midvidy

766-783

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Easy Explicit Coupling Between Two Large Codes Using CRAY UNICOS

G. Nicolas, E. Briere, F. Lux, S. Marguet

784-796

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Simulation of the Long Term-Cooling Behaviour After a PWR Loss of Coolant Accident Using RELAP5/MOD2

G. Willmott, M. El-Shanawany

797-804

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Three-Dimensional Simulation of Jet Flow Impacting onto a Plate Inside an Enclosure

A.K. Ahluwalia, A.M. Chan

805-818

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Prediction of Pressurizer Transients by the IDRIFF Two-Phase Simulation Code

R. Sollychin, W.J. Garland

819-844

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Simulation of Feed/Bleed Operation in AGS Dew Point Monitoring

J.M. Kenchington, A. Choi, D.G. Meranda

845-865

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Detailed Simulation of the Refuelling Operation for a Single Fuel Channel Using RFSP

M.A. Milley, C. Newman

866-890

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Enhancements in FMDP Spatial-Control Algorithm and Xenon Time Search

M.C. Beaudet, D.A. Jenkins

891-895

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CANDU Reactor Regulating System Response Modelling in SMOKIN Code

M.Z. Farooqui, M.B. Gold

896-912

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Improved Method for Calculation of Hannonic Modes for CANDU Reactors

N. Roy, S.D. Arguner, A.U. Rehman, A.L. Wight

913-923

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Optimization of Marine Pressurized Water Reactor In-Core Fuel Management

S.Keith Dewar, Hugues W. Bonin

924-945

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Preliminary Thermalhydraulics Analysis of the AMPS-1000 Reactor Using COBRA-IV and RELAP5/MOD2

A. Tahir, V. Tavasoli

946-969

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Application of FLOW3D to Flow Modelling in Small Pool Natural-Circulation and Forced-Circulation Reactors

S.J. Marshall, M.B. Carver, P.W. Shipp

970-984

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Numerical Prediction of Transient Thermalhydiaulic Behaviour of a Maple Finned Fuel Element Simulator

P.J. Mills, S.Y. Shim

994-996

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Dynamic Modelling of Primary Heat Transport System of KMRR for Real Time Plant Simulation

Bo-Wook Rhee, K.H. Lee, B.S. Sim, S.K. Oh

985-991

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Three-Dimensional Calculations of Low-Flow Buoyant Jets in a Maple Flow Test Facility

S.Y. Shim, D.K. Baxter

992-993

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Predicting the Distribution of Fuel Temperatures for a Single Channel Flow Blockage Scenario Using the Newly Developed Code CANSIM-PLE

K.E. Locke, A.P. Muzumdar, L.J. Watt, V.J. Langman

997-1024

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FROMSFD: Transient Zircaloy Oxidation by Steam With Reduction of Urania

L.D. Macdonald, D.F. Simmons, F.C. Iglesias, D.B. Duncan

1025-1028

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Two-Dimensional Finite-Element Analysis of Fin Efficiency for Finned Fuel Pin

G.D. Harvel, S.Y. Shim, P.J. Mills

1029-1031

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Zircaloy Clad Failure Simulation in Rod Bundles Under LOCA Conditions

Nicholas T. Saltos

1032-1054

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ANSYS Thermal Analysis of Bearing Pad/Pressure Tube Interface

A.P. Muzumdar, G.R. Berzins, M. Krause, J.W. DeVaal

1055-1075

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Sweep-Gas Experiment Interpretation and Freedom Code Validation

L.D. Macdonald, F.C. Iglesias, D.B. Duncan, Brent J. Lewis

1076-1080

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Influence of Graphite Discs, Chamfers, and Plenums on Temperature Distributions in High Burnup Fuel

A. Ranger, M. Tayal, P. Singh, I.A. El-Osery, K.A. Yasso

1081-1101

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Status of Natural Circulation Experiments in Multiple Channel RD-14M Test Facility

P. Gulshani, J.N. Barkman, H. Huynh, M.A. Wright

1102-1126

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TREAT Reactor Control Rod Scram System Simulations and Testing

C.W. Solbrig, W.W. Stevens

1127-1148

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