Published: 1993-10-06

Articles

Advances in Nuclear Steam Generator Technology for Improved Reliabilily

James C. Smith
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Loser Welded Sleeving - A Proven Technology for Steam Generator Life Enhancement

Bala R. Nair
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A Horizontal Stem Generator for Indian 235-MW Heavy-Water Nuclear Power Plants

D.R. Iyer
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A Kinetic Model for Fission-Product Release and Fuel Oxidation Behaviour for Zircaby-Clad Fuel Elements Under Reactor Accident Conditions

Brent J. Lewis, D.S. Cox, F.C. Iglesias
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The Importance of Organic Compounds in Evaluating Accident Management Strategies

Claudio A. Chuaqui, Joanne Ball, Richard Fluke, Jeremy Edward, K. Weaver
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The Radiolysis of Aqueous Organic Systems and Its Effect on Iodine Volatility

Raymond C. Quan, Mehdi Mesbah-Oskui, Greg J. Evans
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A Neural Network Model of Volatile Fission Product Release from Fuel Elements and Fragments Under Severe Accident Conditions

W.S. Andrews, Brent J. Lewis, D.S. Cox
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HUEMUL A Transport Code for General Geometries Including Reactivity Devices - Its Validation Against Measurements

Carlos Ruben Calabrese, Carlos Grant, Ana Maria Lerner, Carla Notari, Oscar Serra
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A General Comparison of the Lottice Codes APOLLO-2 and DRAGON

Alain Hebert
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Burnable Poison: A Solution for Fuel Management in 1.2% SEU Fueled CANDU 6 MKI Core

D. Serghiuta, E. Nichita, O. Nainer, P. Laslau
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Selection of Materials with Low Induced Activity Following Neutron Irradiation

K.T. Tsang, C.R. Boss
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Improvements in the Fracture Toughness of CANDU Zr-2.5 Nb Pressure Tubes

G.D. Moan, J.R. Theaker, P.H. Davies, I. Aitchison, C.E. Coleman, R.A. Graham, S.A. Aldridge
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Nuclear Sources of Hydrogen in CANDU Fuel Channels

M. Aslam Lone
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Using Improved Elastomers To Enhance CANDU Station Reliability

R. Wensel
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A Versatile Electrical Penetration Design Qualified to IEEE Std 31 7-1983

William Lankenau, Todd Wetherill
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Mineralogical and Corrosion Problem Underlying the Choice of Materials for High-Level Nuclear Waste Disposal

M.B. McNeil, T.L. Woods
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Role of the Geosphere in the Canadian Concept for Nuclear Fuel Waste Disposal

C.C. Davison, F.P. Sargent, S.H. Whitaker
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Fully Treated and Solidified Radioactive and Hazardous Wastes Belong in an Above-Grade, Earth-Mound, Concrete Disposal Vault

G. Ross Darnell
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Long-Term Safety Assessment of the Disposal of Nuclear Fuel Waste

K.W. Dormuth, B.W. Goodwin, A.G. Wikjord
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AECL's IMPEL Electron Accelerators for Industrial Uses

Andrew J. Stirling
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Advances in Radiation Processing of Polymeric Materials

K. Makuuchi, T. Sasaki, A.C. Vikis, A. Singh
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Effects of High Radiation Environments on Polymer Composite Epoxies

H.W. Bonin, H.M. Pak, V.T. Bui, D. RhCaume
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Some Calculational Results for Transmutation of Plutonium and Wastes in Blankets of Accelerator-Based Systems

B.P. Kochurov
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Coping with Human Factors in Nuclear Power Plants

Jean-Pierre Clausner
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Framework for Human Factors Input to Design Projects

Johanne Penington
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A Tool to Assist in Plant Data Monitoring and Diagnostics

P.D. Thompson, M.K. Gay, C. Xian, J.W. Thompson
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Performance Support Systems and Artificial Intelligent Considerations

W.F.S. Poehlman, W.J. Garland, A.A. Bokhari, C.W. Baetsen, R.J. Wilson
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Reduction of Pressure-Tube to Calandria-Tube Contact Conductance to Enhance the Passive Safety of a CANDU-PHW Reactor

D.B. Sanderson, R.G. Moyer, D.G. Litke, H.E. Rosinger, S. Girgis
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Simulation of the Pressure-Tube Circumferential Temperature Distribution Experiments (Variable Make-Up Water Experiments)

M.H. Bayoumi, P.S. Kundurpi, W.C. Muir
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Liquid Relief Valve Failure Simulation in the Embalse Nuclear Power Station

Sara Gersberg, J.R. Lorenzetti, D. Parkansky, J. Batistic
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Simulation and Analysis of a Main Steam tine Transient with Isolation Valves Closure and Subsequent Pipe Break

Vladimir Stevanovic, Milovan Studovic, Aleksandar Bractic
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Flux Mapping Theory Application for Channel Power Prediction

D. Brissette, M. Beaudet
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A Review of the History-Based Local-Parameter Methodology for Sirnulatifig CANDU Reactor Cores

B. Rouben, D.A. Jenkins
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Validating the History -Based Diffusion Methodology for Core Tracking Using in-Corc Detectors

A.C. Mao, B. Rouben, D.A. Jenkins, E. Young, C. Newman
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On-Line Hear Deposition Rate Measurements with a Quasi-Adiabatic Graphite Calorimeter in a Fusion Environment and Comparison with Calculations

O.P. Joneja, J.-P. Schneeberger, R.P. Anand, T. Buchillier
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Planning the Retubing of a CANDU 6 Reactor

N.G. Craik, R. Baker
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Improvements in Remote Removal Techniques for Active Components during Large-Scale Retubing of CANDU Reactors

W.J. Knowles
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Developments in Orbiting Took for Refurbishment of CANDU Fuel Channel Components

Mark Pollock
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CANDU Single- Fuel-Channel Replacement Reducing Time and Radiation Exposure

T.A. Hunter, D.R. Pollock
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Progress at AECL's Underground Research Laboratory

Gary R. Simmons
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The Role of Engineered Barriers in the Disposal of Nuclear Fuel Waste - The Canadian Perspective

K. Nuttall, L.H. Johnson
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Sulfur Polymer Cement, A Solidification and Stabiliution Agent for Radioactive and Hazardous Wastes

G. Ross Darnell
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The Cigar Lake Analog Study: An Intemational R&D Project

Jan J. Cramer, F. Peter Sargent
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Nuclear Data for Feasibility Assessment of HLW Transmutation

M.A. Lone, P.Y. Wong, W.J. Edwards, R. Collins
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Neutron Activation Analysis of Mortars from Stone Houses Built in Canada During thc French Rkgirne

H.W. Bonin, C. Bordeleau, J.R.M. Boule, M.A.T. Lapointe
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Handled Gamma Quant Generator in Density Measurement

Alexander Mozelev
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Technology-Assisted Training in the Nuclear Regulatory Environment

D.J. Martin
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Alarm Processing for Diagnosis Using a Holographic Neural Network (HNeT)

J.E. Smith, M. Schwarzblat, J.G. Sutherland
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The Design and Implementation of an Operator's Performance Support System

R.J. Wilson, A.A. Bokhari, W.J. Garland, W.F.S. Poehlman, C.W. Baetsen
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Training Program Evaluation: Current Regulatory Activities

D. Tennant, R. Droll
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A Turbine Trip Transient Analysis with TRAC-BF1

Juan Luis Francois
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Should We Install a Software-Based Reactor Protection System?

Geoffrey Ives
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Operating Under Fire the French Way

F. Bediou, J.P. Chatry
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Nuclear Plant Safety Enhmcement by Early Identification of Slow Developing Abnormal Processes

V. Kotelenets, S. Korolev, M. Konovich
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