Published: 1995-06-07

Articles

Stability of Interracial Waves in Two-Phase Flows

W.S. Liu
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New Data on Two-Phase Water-Air Hydrodynamics in Vertical Upward and Downward Flows

V. Lau, K.S. Rezkallah
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An Experimental Study of a Flashing-Driven CANDU Moderator Cooling System

H.F. Khartabil, N.J. Spinks
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RELAP5 Simulations of Critical Break Experiments in the RD-14 Test Facility

In-Goo Kim, Yong-Jin Cho, Sukho Lee
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MMOSS-I: A CANDU Multiple-Channel Thermosyphoning Flow Stability Model

P. Gulshani, H. Huynh
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Modelling Disassembled Fuel Bundles Using CATHENA MOD-3.5a Under LOCA/LOECC Conditions

Q.M. Lei, D.B. Sanderson, R. Dutton
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Laminar Burning Velocities of Near-Flammability-Limit H2-Air-Steam Mixtures

J.V. Loesel Sitar, C.K. Chan, F. Torchia, A. Guerrero
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Effect of Turbulence on Deflagration to Detonation Transition

D.D. Radford, C.K. Chan, R.S. Azad
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Improved Containment Isolation for CANDU Plants

A.H. Stretch
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Modelling of Reactor Air-Cooling Equipment Under Accident Conditions

Sunil Nijhawan
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CANDU Containment Leakage Considerations

J.K. Biswas, M. Ahmad
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Addressing the Alarm Analysis Barrier - A Tool for Improving Alarm Systems

E.C. Davey, R.A. Basso, M.P. Feher
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The Human Factors Engineering Program Plan

J. Jamieson
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Development and Applications of Reactor Noise Analysis at Ontario Hydro's CANDU Reactors

O. Glockler, M.V. Tulett
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A Design Basis for the Development of Advanced CANDU Control Centres

M.P. Feher, E.C. Davey, L.R. Lupton
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Advanced Operator Interface Design for CANDU-3 Fuel Handling System

Damodar Arapakota
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CANDU Physics Considerations for the Disposition of Weapons-Grade Plutonium

John Pitre, Peter Chan, Adi Dastur
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A DRAGON-MCNP Comparison of Void Reactivity Calculations

Guy Marleau, M.S. Milgram
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Capability to Model Reactor Regulating System in RFSP

H.C. Chow, B. Rouben, M.H. Younis, D.A. Jenkins, A. Baudouin, P.D. Thompson
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Sensitivity of Self-Powered Detector (SPD) Probes to Electron and Gamma-Ray Fields

M.A. Lone, P.Y. Wong
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A Comparison of LOCA Analysis Using SMOKIN and CERBERUS Codes

M.H. Younis, G. Gaboury
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Calculation of Homogenized Pickering NGS Stainless Steel Adjuster Rod Neutron Cross-Sections Using Conservation of Reaction Rates

R.C. Robinson, F. Tran
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The Canadian Initiative to Host the International Thermonuclear Experimental Reactor

D.P. Dautovich, R.A. James
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Studies on Acoustic Modelling Techniques for CANDU Reactors

V. Chatoorgoon, R. Zhou
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Fuel Bundle Movement due to Reverse Flow

N.N. Wahba, O. Akalin
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Investigation into the Modelling of the Effect of Pressure Tube Creep on CHF, Dryout Power and Pressure Drop

M.R. Soulard, R. Dam, M. Carver, G. Hotte, R.A. Gibb
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Prediction of CANDU-6 Moderator System Response Following a Large Break LOCA Using a 3D Model

T.K. De, W.M. Collins, R.W. Holmes
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Experimental Investigation into Consequences of Fuel Channel Failure in a CANDU Reactor Under Normal Operating Conditions

G.I. Hadaller, P.F. Sandig, P.S. Kundurpi
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Experimental Study on the Effect of Heat Flux Tilt on Rod Bundle Dryout Limitation

Satoru Sugawara, Kohji Terunuma, Hiroshi Kamoshida
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Experiment on the Effects of Contact Between the Pressure Tube and the Fuel Assembly

Yuji Watanabe, Yoshihiro Fujii, Kouhei Kato
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Prediction of Pressure Tube Fretting-Wear Damage due to Fuel Vibration

Metin Yetisir, N.J. Fisher
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Fuel Channel Design Improvements for Large CANDU Reactors

A. Villamagna, E.G. Price, G.J. Field
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Simulation and Analysis of Bearing Pad to Pressure Tube Contact Heat Transfer Under Large Break LOCA Conditions

M.H. Bayoumi, W.C. Muir, P.B. Middleton
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A Neutron Scattering Device for Void Fraction Measurement in Channels of the RD-14M Thermalhydraulics Test Facility

P. Han, E.M.A. Hussein, P.J. Ingham
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Experimental Technique for Testing CANDU Fuel Channel Components at High Rates of Strain

D.D. Radford, E.K. Bueckert
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State of the Art Seismic Analysis for CANDU Reactor Structure Components Using Condensation Method

S.A. Soliman, A.M. Ibrahim, S. Hodgson
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A Study on the Long-Term Properties of Concrete

Young-Chul Song, Dae-Soo Lee, Myung-Suk Cho, Jang-Hwa Lee
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Thermalhydraulic Analyses of AECL's Spent Fuel Dry Storage Systems

R. Moffett, G. Sabourin, A.O. Banas
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Effects of Neutrons and Gamma Radiation on High Polymer Epoxy Adhesives

H.W. Bonin, V.T. Bui, P.E. Poirier
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AUTO-LAY: Automatic Layout Generation for Procedure Flow Diagrams

P. Forzano, P. Castagna
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Life Assurance of CANDU Calandria and Shield Tank Assemblies

T.G. Richards, W.Z. Novak
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Deterministic LOCA Avoidance by Gravity Effect

A.A. Harms
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The 1994 Loss of Coolant Incident at Pickering NGS

P.R. Charlebois, T.R. Clarke, R.M. Goodman, W.F. McEwan, J.M. Cuttler
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The Fuel String Relocation Effect - Why the Bruce Reactors Were Derated

M. Gold, M.Z. Farooqui, A.S. Adebiyi, R.Y. Chu, N.T. Le, A.F. Oliva, G. Balog, T. Qu, P.G. deBuda
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Bruce and Darlington Power Pulse and Pressure Tube Integrity Programs - Status 1995

G.J. Field, J. Wylie
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Integrated Burst Tests - Recent Experimental Investigation into Consequences of Pressure Tube / Calandria Tube Failure

G.I. Hadaller, P.F. Sandig, P.S. Kundurpi, G.R. Berzins
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Application of Up-Front Licensing

Scott D. Grant, Victor G. Snell
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Use of Operational Data for the Validation of the SOPHT Thermal-Hydraulic Code

S.F. Ho, G. Martin, L. Shoukas, Z. Siddiqui, B. Phillips
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TUF Simulation of Darlington Class IV Power Failure

W.K. Liauw, W.S. Liu, R.K. Leung, B.S. Phillips
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Thermal Hydraulic Analysis of Steam Generators: Application of the THIRST Code to Vibration Analyses

J.M. Pietralik
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Dual Discharge from a Stratified Two-Phase Region Through Side Orifices Oriented Horizontally

I.G. Hassan, H.M. Soliman, G.E. Sims, J.E. Kowalski
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Stress Analysis for CANDU Reactor Structure Assembly Following a Postulated P/T, C/T Rupture After Flow Blockage

S.A. Soliman, T. Lee, A.M. Ibrahim, S. Hodgson
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Simulation and Analysis of the Thermal and Deformation Behaviour of 'As-Received' and 'Hydrided' Pressure Tubes Used in the Circumferential Temperature Distribution Experiments (End of Life/Pressure Tube Behaviour)

W.C. Muir, M.H. Bayoumi
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Fuel Bundle to Pressure Tube Fretting in Bruce and Darlington

A.G. Norsworthy, A. Ditschun
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Development, Verification and Validation of the Fuel Channel Behaviour Computer Code FACTAR

C.J. Westbye, A.C. Brito, J.C. Mackinnon, H.E. Sills, V.J. Langman
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Key Methods for Sustaining Quality Engineering Data in Nuclear Power Plants

Alan Cook
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Modularized Construction, Structural Design and Analysis of CANDU 3 Plant

J.K. Biswas, S. Wollin, S. Selvadurai, A.M. Saudy
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Bruce A Unit 1 Moderator to End Shield Cooling Leak Repairs

Paul Boucher, Al Ashton
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Preparation of Wet-proofed Catalyst for Tritium Removal

Soon-Hwan Son, Gab-Bock Lee, Myung-Jae Song
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Development of Aquatic Plant Bioassays for Rapid Screening and Interpretive Risk Assessments of Metal Mining Liquid Waste Waters

Hans G. Peterson, Niels Nyholm, P. Ming Huang
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Interactions of Molten Zircalloy Droplets with Water

Sunil Nijhawan, Charles Blahnik
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MAAP CANDU Simulation of Severe Accidents in Darlington Nuclear Generating Station

M. Kwee, M. Choi, R. Leung, S.G. Lie
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Results of the CANDU 3 Probabilistic Safety Assessment

R.K. Jaitly
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Approach for Seismic Risk Analysis for CANDU Plants in Korea

Beom-Su Lee, Taeyun Kim, Sun-Koo Kang, Sung-Yull Hong, Sung-Rai Roh
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Accelerator Mass Spectrometry of 36Cl at TASCC: Applications to Nuclear Problems

H.R. Andrews, L. Chant, R.J.J. Cornett, W.G. Davies, B.F. Greiner, Y. Imahori, V.T. Koslowsky, S. Kramer, J.W. McKay, G.M. Milton, J.C.D. Milton
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Research Reactors Role in KOREA

Chang-oong Choi
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A Description of the Canadian Irradiation-Research Facility Proposed to Replace the NRU Reactor

A.G. Lee, R.F. Lidstone, W.E. Bishop, E.F. Talbot, H. McIlwain
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Fuel Alternatives for Oil Sands Development - The Nuclear Option

David Bock, John K. Donnelly
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CANDU Product Development

Ken R. Hedges
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Radiation: Is Risk Really Proportional to Dose?

R.E.J. Mitchel
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Developing a Biological Dosimeter Based on Mitochondrial DNA

S. Adams, S.M. Carlisle, P. Unrau, K.V. Deugau
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An Accident Involving Transport of Radioactive Materials, Canada, 1994 March

Frank Keeling, Lloyd E.G. Dunn
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Developments in Biological Dosimetry for the Nuclear Industry

K.L. Gale, D.R. Boreham, S. Maves, D.P. Morrison
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Radiation Shielding Analysis for the Pickering Used Fuel Dry Storage Facility

H. Roman, C.A. Morrison
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Characteristics of CANDU Bundies that Caused Pressure Tube Fretting at the Bundle Midplane

D. Dennier, A.M. Manzer, E. Kohn
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The Lumped Parameter Model for Fuel Pins

W.S. Liu
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Post-Test Simulation and Analysis of the Second Full Scale CHAN 28-Element Experiment (Validations of CHAN-II (Mod 6) Against Experiments)

M.H. Bayoumi, W.C. Muir
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Studies of Irradiated Zircalloy Fuel Sheathing Using XPS

P.K. Chan, K.G. Irving, W.H. Hocking, A.M. Duclos, A.F. Gerwing
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Preliminary Results of the BTF-104 Experiment: An In-Reactor Test of Fuel Behaviour and Fission-Product Release and Transport under LOCA/LOECC Conditions

L.W. Dickson, P.H. Elder, J.W. DeVaal, J.D. Irish, A.R. Yamazaki
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Development of a Test Rig and its Application for Validation and Reliability Testing of Safety-Critical Software

N.D. Thai, A.M. McDonald
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Determining the Confidence Levels of Sensor Outputs Using Neural Networks

Gregory S. Broten, H.C. Wood
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PROMO: A Computerized Tool to Support Process Monitoring Activities - Applications in CANDU Simulators

Daniele Thomassin Singh, Pavan Pratap Singh
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