Published: 2008-06-01

Articles

Sustainable Development - Opening Address 29th Annual Canadian Nuclear Society Conference

P. Lamarre
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Pressure Tube Reactors and the Sustainable Energy Future: the Ultra Development Path

Romney B. Duffey
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Nuclear Regulation and Generation III Reactors

John G. Waddington
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The ACR-1000 Fuel Design Verification Process

Patrick Reid, Mukesh Tayal, Milan Gacesa
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Molten Salt Reactors: a New Vision for a Generation IV Concept

David LeBlanc
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The Pebble Bed Modular Reactor (PBMR) as a Source of High Quality Process Heat for Sustainable Oil Sands Expansion

Antony Morris, R. Kuhr
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Laser Peening Applications for Next Generation of Nuclear Power Facilities

John Rankin, Chanh Truong, Matt Walter, Hao-Lin Chen, Lloyd Hackel
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BNA Pellet Material Properties Test Program in Support of ACR-1000 Fuel Design

J. Chang, Z. He, Milan Gacesa, Patrick Reid
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Zirconia-rare Earth Oxide Phase Stability Program in Support of ACR-1000® Fuel Design

J. Hood, F. Akbari, Z. He, Patrick Reid, Emily Corcoran, Brent J. Lewis, W.T. Thompson
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The Latest Application of Hitachi-GE’s State-of-the-Art Construction Technology and Further Evolution Towards New Build NPP Projects

Kenji Akagi, Kensuke Morita, Ryohei Miyahara, Kouichi Murayama, Christopher Deir, Shiro Akahori
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Steam Generator Deposit Mapping

Victor F. Newman
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Hydraulic Nuts (HydraNuts) for Critical Bolted Joints

Steve Greenwell
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An Analysis to Determine Industry's Preferred Option for an Initial Generic Reliability Database for CANDU

Dragon Komljenovic, Eliseo Chan, Sugata Ganguli, Jie Wu, Ranbir Parmar
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Best Practices in Design and Delivery of a New Tritium Facility

I. Bonnett, A. Busigin, A. Griffiths
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Use of Soft-Metal Engineered Surfaces to Minimize Galling of Carbon Steel Bolting Materials in Gasketed Joints at Elevated Temperatures

Daniel N. Hopkins, Craig D. Harrington, Steve Greenwell
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Generic and Profile Specific Feeder Stress Analysis

M. Li, M.L. Aggarwal
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Aqueous Solubility of Zirconia

S. Sunder, Sumi Wren
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Simulation of High-Temperature, Non-Congruent Phase Transitions in UO2+x

M.J. Welland, W.T. Thompson, Brent J. Lewis
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Computed Phase Equilibria for Burnable Neutron Absorbing Materials for the Advanced CANDU Reactor Design

Emily Corcoran, Brent J. Lewis, W.T. Thompson
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New Shielding Materials With Advanced Gamma Absorption

S.G. Ermichev, O.I. Yuferov, V.I. Shapovalov, V.M. Sergeev, A.G. Semenov, V.K. Orlov, A.I. Morenko, V.Z. Matveev, A.A. Maslov, A.M. Visik
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A Transient Neutronic-Thermalhydraulic Coupled Modelling Approach

Majid Fassi Fehri, Richard Chambon, Alberto Teyssedou
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Validation of Impinging Jet Models to Be Used in CANDU Calandria Vessel CFD Simulations

Martin Bouquillon, Alberto Teyssedou, Eugenio Cuesta, Hong Huynh
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Experimental Investigation of Flow Obstacles Effect on Single Phase Heat Transfer

Aurelian Tanase, D.C. Groeneveld, Hussam Zahlan, S.C. Cheng
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Fluid-Phase Transitions in Light Water and Heavy Water

R.L. Varty
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Investigation of the Combined Effect of Appendages and Axial Power Profile on Post-Dryout Heat Transfer in Tubes

Hussam Zahlan, D.C. Groeneveld, L.K.H. Leung, Aurelian Tanase, S.C. Cheng
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Modeling the Quenching of a Calandria Tube Following a Critical Break LOCA in a CANDU Reactor

J.T. Jiang, John C. Luxat
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Modeling of Pickering NGS B Heat Transport System Seismic Boundary Leak Tightness Test

R. MacLeod, Carlos Lorencez
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Overview of Experimental Programs on Core Melt Progression and Fission Product Release Behaviour

Brent J. Lewis, R. Dickson, Fernando C. Iglesias
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How Safe Is Safe Enough? The Canadian Answer

Fred Boyd
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Fission Product Release Mechanisms: Research in Canada

Fernando C. Iglesias, Brent J. Lewis, A. Oliva, P. Purdy
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Using Statistical Inference for Decision Making in Best Estimate Analyses

Paul Sermer, K. Weaver, Fred Hoppe, C. Olive, Dan Quach
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Determination of Realistic Margins to Fuel Heatup for Slow Loss of Regulation Accidents in a CANDU Reactor

David R. Novog, Paul Sermer, Dan Quach, John C. Luxat
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First Steps Toward a Mechanistic Model for Core Disassembly in a CANDU Reactor

R. Perez
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Pressure Tube-Calandria Tube Thermal Contact Conductance

A. Cziraky
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Intergranular Corrosion Mechanism of Alloy 400

W. Zhang
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The Kinetics of Cathodic Oxygen Reduction on Thin Films on Ni-Cr-Mo (W) Alloys

X. Zhang, P. Jakupi, D. Zagidulin, J.J. Noël, D.W. Shoesmith
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Fuel Performance and Thermochemistry Modeling of Candu Nuclear Fuel Progress in Developing a Self Standing Integrated Code

M.H.A. Piro
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A Simplified Oxidation Model for Defective Nuclear Fuel

K. Shaheen
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Modification of Fuel Bundles and Associated Optimization of Fuel Handling Equipment

Paul Ponomaryov
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Modelling of Aircrew Radiation Exposure From Solar Particle Events

Hani AlAnid, Brent J. Lewis, L.G.I. Bennett
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Environmental Monitoring of Chinook Salmon

Dale Morris, Doug R. Boreham
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Diagnostic Imaging Procedures During Pregnancy: What Are the Fetal Risks?

K. Taylor
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Effects of Low-Dose Gamma and Neutron Radiation on Genotoxicity and Cytotoxicity of Reticulocytes in a Mouse Model

Nghi Phan, Nicole M. McFarlane, Jennifer Lemon, Doug R. Boreham
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Effet d’une vidange stratifiée du caloporteur sur la réactivité et la distribution du flux neutronique d’une cellule CANDU-6

M. Massicotte
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Time Average CANDU Model With Fuel Reshuffling

K. Auyeung, S. Kelley, R. Godavarthi
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Process Simulation of Nuclear-based Thermochemical Hydrogen Production With a Copper-Chlorine Cycle

C.C. Chukwu, Greg F. Naterer, Marc A. Rosen
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Safety Issues in Nuclear Hydrogen Production With the Very High Temperature Reactor (VHTR)

Satyen Baindur
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Life Cycle Assessment of Nuclear-Based Hydrogen Production Using Thermochemical Water Decomposition: Extension of Previous Work and Future Needs

Luthfi I. Lubis, Ibrahim Dincer, Marc A. Rosen
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Application of Multi-state Systems in Fault Tree Analysis of a Conceptual Thermochemical Hydrogen Plant

Y. Zhang, L. Lu, Greg F. Naterer
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Energy and Exergy Analyses of a Copper-Chlorine Thermochemical Water Decomposition Pilot Plant for Hydrogen Production

M.F. Orhan, Ibrahim Dincer, Marc A. Rosen
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Hydrodynamics of Cupric Chloride Hydrolysis in a Fluidized Bed for Nuclear Hydrogen Production

Y. Haseli, Ibrahim Dincer, Greg F. Naterer
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Thermochemical Process Heat Requirements of the Copper-Chlorine Cycle for Nuclear-Based Hydrogen Production

Z. Wang, Kamiel Gabriel, Greg F. Naterer
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An Introduction to a New IAEA Safety Guide: "Aging Management for Nuclear Power Plants"

J. Pachner, T. Inagaki, K.-S. Kang
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Canadian Regulatory Oversight of Ageing Management for Nuclear Power Plants

K. Kirkhope, A. Blahoianu, G. Frappier
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Plans to Adapt Point Lepreau Ageing Management to New Industry Guidelines

G. Greenlaw, Tracy Gendron, J. Slade, B. Rankin
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Current & Future Ultrasonic Inspection For CANDU® SG Tubes

Z. Chen, K. Chan, J. Huggins, T. Malkiewicz
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STANPIPES Moves to the Windows Environment

Tom Stevens, Bruce Manning
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Ultrasonic Inspection of Tubes Without Rotation

A. Karpelson
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Cable Condition Monitoring Using Non-Destructive and Non-Intrusive Fourier Transform Near Infrared (FT-NIR) Spectroscopy

Hormoz Azizian, S. Benson
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New Laws of Practice for Learning and Error Correction

Romney B. Duffey
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Human Factors in the Canadian Nuclear Industry: Future Needs

Felicity Harrison
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Providing Operator Support During Monitoring for Unanticipated Events Through Ecological Interface Design

Nathan Lau, Greg A. Jamieson, Gyrd Skraaning, Catherine M. Burns
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The Practical Aspects of Incorporating HF Considerations Into Design Changes at Nuclear Facilities - A Contractor’s Perspective

M. Hourihan, M. Remisz, P. Spagnolo
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Utilization of Handheld Computing to Trend Improvements in Compliance

G. Galvin, J. Rasmussen, A. Haines
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Development of Public Acceptance and Market Success With Very Small Nuclear Power Reactors (VSR)

P. Lang
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RFSP-IST Simulation of Fuel Transient During Refuelling of the ACR-1000 Reactor

J. Hu, Iouri Martchouk, R. Robinson
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Void Reactivity Studies for the ATUCHA-II PHWR Reactor - Preliminary Design of a Lower Void Reactivity Fuel

F. Khatchikian, J. Fink
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Modifications for Better Control of the First Radial Mode During Load-Cycling of the ACR-1000

G Teneva, R. Robinson
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Utilization of Simulated Annealing Algorithm in the ROP Detector Layout Optimisation

Doddy Kastanya, Victor Caxaj
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Improvement and Qualification of WIMS Utilities

T. Liang, W. Shen, Elisabeth Varin, K. Ho
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Comparison of Bare-Lattice Calculations Using MCNP Against Measurements With CANFLEX®-LEU in ZED-2

Y. Dweiri, B. Arsenault, Michael B. Zeller
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Improved Linear Congruential Random Number Generators

Huayun Shen, Peng Zhang, Kan Wang
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Fundamental Bop I & C Systems Structure in Nuclear Power Plants

K. Ishii, H. Harada, T. Yamamori, K. Igarashi, T. Arakida
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Research on Visual Modeling and Simulation Method for Operational Flowsheets-oriented CANDU Control Systems

Zhenhua Cui, Robyn Prime, K. Scott, M. McIntyre
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Online Control Loop Tuning in Pickering Nuclear Generating Stations

Kevin X. Yu, Stephen Harrington
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Thermal Gradients Caused by the CANDU® Moderator Circulation

Virender Mohindra, Marius Andrei Vartolomei, Roland Scharfenberg
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Modifications to Improve Reliability in Deaerator Level Control by Using Digital Technology

Stephen Harrington, Kevin X. Yu
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Reactor Building Indoor Wireless Network Channel Quality Estimation Using RSSI Measurement of Wireless Sensor Network

Soorena Merat
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Effects of Fluid Stream Impurities on Performance of a Supercritical Co2 Power Conversion System

D. Côté, A. Gagnon, D. Pucsek
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Numerical Investigation of Turbulent Flow in a Twin Rectangular Sub-channel Geometry

D. Home, Marilyn F. Lightstone, Mohamed S. Hamed
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Unsteady Reynolds Averaged Navier-Stokes (URANS) Modelling of Turbulent Flow in a Twin Rectangular Subchannel Geometry

G. Arvanitis, D. Home, Marilyn F. Lightstone, Mohamed S. Hamed
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Novel Design of a CHF Experimental Facility

B.A. Statham
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Validation of Fluent Software for Prediction of Flow Distribution and Pressure Gradients in a Multi-Branch Flow Header

A. Muhana, David R. Novog
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An Approach to Modelling the Effects of a Small LOCA With a Loss of ECI Under Natural Circulation Conditions in a CANDU Reactor

D. Pohl
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Literature Investigation of Air/Steam Ingress Through Small Cracks in Concrete Wall Under Pressure Differences

J.T. Jiang
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IEC 61508: Compatibility, Application and Requirements in Canadian Nuclear Industry

Elyad Zahedi
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Radiolysis of Water Containing Dissolved Nitrogen Species

Pam Yakabuskie, Jiju M. Joseph, J. Clara Wren
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Effect of Gamma Radiation on Steel Corrosion

K. Daub, X. Zhang, J.J. Noël, D.W. Shoesmith, J. Clara Wren
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Film Breakdown Processes on Carbon Steel in the Presence of Large Anions

Katayoun Yazdanfar
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Metal-oxide Film Conversions Involving Large Anions

S. Pretty, X. Zhang, D.W. Shoesmith, J. Clara Wren
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Electrochemical Impedance Spectroscopy Study of H2O2 Interaction With Γ-FeOOh Single-phase Films on the Gold Electrodes

D. Fu
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The Determination of Local Corrosion Kinetics Using Scanning Electrochemical Microscopy

Heming He, Z. Qin, P.G. Keech, J.J. Noël, Z.F. Ding, D.W. Shoesmith
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Crevice Corrosion Damage Analysis on Ni-Cr-Mo Alloys Proposed for the Nuclear Waste Containers

P. Jakupi, D. Zagidulin, J.J. Noël, D.W. Shoesmith
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Surface Electrochemistry of UO2 in Dilute Acidic Hydrogen Peroxide Solutions

D. Hall, P.G. Keech, J.J. Noël, D.W. Shoesmith
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COG's Contribution to the Industry

J. Froats
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Tacit Knowledge Emergence

W. Garland
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Human Resources - Meeting the Challenge: an Organization of CANDU Industries Perspective

Martyn Wash
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Women and the Nuclear Talent Pool: Myths and Perspectives on the Present and Future

S. Brissette, B. Keenan
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Implementation of a Comprehensive Program to Deal With Canada’s Nuclear Legacy Liabilities: A Progress Report

J. Miller, D. Metcalfe, A. Melnyk, G. Koroll, S. Kenny, P.J. Ingham, G. Dolinar, S. Brooks, S. Halpenny, M Blanchette
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Commercial Implementation of an Innovative Multi-stage Treatment System for Removal of Radiological and Chemical Contaminants to Near-Zero Levels

Ram Davloor, Bill Harper, Doug Bastien, Jim Rapley
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Over-Packing of Spent Ion Exchange Resin Carbon Steel Liners at Ontario Power Generation’s Western Waste Management Facility

Aamir Husain, D. Pearson, Ben Sklar
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Environmental Assessment Planning for Nuclear New Build in Canada

D. Moffett, M. Mayhew, J. Scongack
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Subduction for Permanent Disposal of Long-lived Highly Radioactive Nuclear Waste

Peter Ottensmeyer
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Degradation and Bacterial Survival on Nuclear-Grade Ion Exchange Resins and Implications for Waste Management

T. Chiappetta, F. Caron, A. Omri
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The Effect of Hydrazine on the Electrochemical Corrosion Potential of Steam Generator Tubing in the Presence of Oxygen

J.M. Smith, A.C. Lloyd
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Cracking of 304L Stainless Steel Observed Within CANDU Nuclear Power Plants Under Cyclic Moist Environments

R.G. Allen, G.I. Ogundele, A.C. Lloyd, D.K. Jain, A.K. Järvine
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Evaluation of Crud Behavior in Primary Circuit of Integral Reactor by Multi-region Model

Byung-Seon Choi, Wan-Young Maeng, Jei-Won Yeon, Jun-Hwa Hong, Ho-Yeon Yang, J. Clara Wren
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A Probabilistic Approach to the Estimation of Lifetime Distribution of Alloy 800 Sg Tubing

Mahesh D. Pandey, S. Datla, R.L. Tapping, Y.C. Lu
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Investigation Into the Potential Release of Chloride From the Moderator Cover Gas Recombiner Catalyst

L. Stolberg, S. Suppiah, K. Kutchcoskie
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Study on the Dissolution of Uranium Dibutyl Phosphate Deposits

A.L. Rufus, V.S. Sathyaseelan, S. Velmurugan, S.V. Narasimhan
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A Keff Calculation Method by Monte Carlo

H. Shen, Kan Wang
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Modelling of Liquid Injection Shutdown System (LISS) in ACR-1000

M. Boubcher, A. Colton, James V. Donnelly
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Comparison of Simulated Radioiodine Ratios With Measured Values for Three CANDU Stations

S. Mostofian, R. Khaloo, C.R. Boss
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Comparison of MCNP Calculations Against Measurements in Moderator Temperature Experiments With CANFLEX-LEU in Zed-2

David G. Watts, Fred P. Adams, Michael B. Zeller, Blair P. Bromley
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Simulation of Long-Term Fuelling Operations for the ACR-1000™

R. Farkas, Ron Robinson, A. Rehman, Adriaan Buijs
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Design of a Guaranteed Shutdown State Using Solid Rods for the ACR-1000 Reactor

I. Hill, James V. Donnelly, Iouri Martchouk, Adriaan Buijs
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Methods for Characterizing Uncertainty Effects in Key Input Parameters Used in the 2-Dimensional Monte-Carlo Simulation of Dryout Power

D. Quach, Paul Sermer, O. Nainer, B. Phan
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Heat Transfer Limitation During Rapid Depressurization

John C. Luxat, David R. Novog
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A Technical Basis for the Flux Corrected Local Conditions Critical Heat Flux Correlation

John C. Luxat
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Application of the Simple Analytical Approach to Calculate Pressure Drop in Liquid Nitrogen Two Phase Flow Over Large Distances Using Hoses

M.A. Aamir, D. Creates, P. Bekeris
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Mock-Up to Simulate Pipe Freezing in Shutdown Cooling Rooms

M.A. Aamir, P. Bekeris, D. Creates
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Multi-Objective Optimization of Thermodynamic Power Cycles Using an Evolutionary Algorithm

W. Hounkonnou, J. Dipama, F. Aubé, Alberto Teyssedou
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Measurements of Turbulent Pressures of Flow in a Water-conveying Pipe Containing a Simulation Fuel Bundle

F. Abbasian, J. Cao, S.D. Yu
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Monitoring and Managing Component Fatigue in CANDU Stations

Metin Yetisir, G.I. Stevens, S. Robertson, Y. Ding, Gordon Burton
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Reactivity Management in Control Room Operations

T. Primeau, A. Dykeman
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Steam Generator Replacement at Bruce A: Approach, Results and Lessons Learned

W. Tomkiewicz, B. Savage, J. Smith
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Evolution of Operations Culture

D. Gould
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Evaluation of Network Structures and Protocols for Nuclear-Specific Applications

Poland Zahedi
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Best Estimate Methods for Safety Analysis and Trip Assessment

Andrew C. Morreale
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Distributed Control System Implementation in Nuclear Power Plants Worldwide: a Literature Survey

Nafisah Khan
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TRIPMAP Generation for McMaster Nuclear Reactor

Kurt Stoll
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Hardware-in-the-Loop (HIL) Nuclear Power Plant Training Simulation Platform Design and Validation

Drew J. Rankin
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