Published: 1990-04-20

Articles

WIMS-AECL: A Review and Status Report

J. Griffiths

1-14

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MODTURC-CLAS: An Efficient Code for Analyses of Moderator Crrculation in CANDU Reactors

R.G. Huget, J.S. Szymanski, P.F. Galpin, W.I. Midvidy

15-32

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Validation of the 2-D Heat Conduction Model in Cathena

D.J. Richards, W.G. Mathers, B.H. McDonald, S.R. Vatsya

33-35

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Implementation of a Control System Test Environment in UNIX

C.R. Brittain, L.A. Rovere, P.J. Otaduy

36-55

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ABRAC: A Microcomputer-Based FORTRAN Code for Multi-Cycle Burnup

Arne P. Olson

56-76

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Reactor Physics Modelling of the Maple Research Reactor

P.A. Carlson, S.G. King

77-93

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Numerical Model for Counter-Current Flow

D.S. Rowe

94-108

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Analysis of Results of Natural Circulation Experiments in RD-14 Multiple Channel Test Facility

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

109-114

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An Analysis of the Lateral Void Transfer Mechanisms in the ASSERT Subchannel Code

P. Tye, A. Tapucu, S. Gencay

115-139

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Recent Extensions to the Capabilities of the Fuel and Wall Models in the ASSERT Subchannel Code

A.O. Banas, M.B. Carver, D.S. Rowe

140-164

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Simulation of Two-Phase Flow Stability Behaviour of CANDU-Typical Heat Transport Systems

J.P. Mallory, P.J. Ingham

165-168

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ASSERT 4 Simulation of the Distribution of Aow, Temperature and Critical Heat Flux in Horizontal Channels at High Pressure

J.C. Kiteley, M.B. Carver

169-191

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Modelling of the Surroundings of MOX Fuel in PWRs

G. Abu-Zaied, P. Grimm, J.M. Paratte

192-206

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The Influence of Plutonium Distribution on the Space-Dependent Kinetics of CANDU

D.H. Chung, A.R. Dastur

207-209

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Simulation of Protective Action by Shutdown-System-1 Against Hypothetical Loss of Coolant From Various Initial Flux Configurations

M.H. Younis, P. Soedijono, A.C. Mao, B. Rouben, M.A. Milley, P.D. Thompson, A. Baudouin

210-238

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Treatment of Circular Boundary Conditions in Neutron Diffusion CaJculations

R. Roy, D. Rozon, A. Hebert, G. Hotte

239-254

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Application of On-Line Solution of3-Dirnensional Multi.group Finite-Difference Neutron Diffusion Equations in Reactor Power Control System

P.S.W. Chan, M. Mamourian

255-279

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CANDU 3 Reactivity Mechanism Deck Shielding Analysis

A. Aydogdu, C.R. Boss

280-301

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Simulation of the Hydraulic Behaviour of TwoPhase Flows in Blocked Subchannels

A. Teyssedou, A. Tapucu, R. Camarero

302-329

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Level Swelling in Pressurizer and Steam Generators

W.S. Liu

330-353

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Calculation of Countercurrent-Flow Flooding Limit Using CATHENA

B.N. Hanna

354-357

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Application of Void Generation and Condensation Models to Predict Subcooled Boiling Data at Low Pressures

V. Chatoorgoon, G.R. Dimmick, M.B. Carver, W.N. Selander, M. Shoukri

358-379

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Interaction of User and Models on System Code Predictions

F. DAuria, G.M. Galassi, P. Lombardi

380-406

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Onset of Flow Stratification in Horizontal RodBundles

S.I. Osamusali, D.C. Groeneveld, S.C. Cheng

407-429

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Simulation of the Plant Controller of LOVIISA Nuclear Power Plant

Kari Porkholm, Markku Hanninen

430-442

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Development of a Robust Model-Based Reactivity Control System

L.A. Rovere, P.J. Otaduy, C.R. Brittain

443-456

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TREAT Reactor Conttol Rod Scram System Simulations and Testing

C.W. Solbrig, W.W. Stevens

457-460

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A Micro-Computer Containment Simulator to Support Training Programs for CANDU Reactor Operators

J.A. Walsworth, E. Kennedy, C.P. Guiry, R.A. Gibb, S.P. Turner

461-485

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MICROSIM: A Real-Time Microcomputer-Based Simulator for Training Nuclear Power Plant Operators

Richard Moffett, Raja Abdallah, Marc Roberge

486-503

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Emergency Management System With Simulation and Training Facilities

Klaus Sjoblom, Berndt Brehmer, Stefan Jakobsson

504-526

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Use of Best Estimate Codes for Analysis of PWR Large Break LOCA

K. Ardron, F.M. Evans, P.C. Hall

527-546

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Simulations of Darlington Shutdown Cooling System

I. Cheng, R.Y. Chu, B. Phillips

547-567

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